Event Notification Report for March 20, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/17/2000 - 03/20/2000

                              ** EVENT NUMBERS **

36703  36806  36807  36808  36809  36810  36811  36812  36813  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36703       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 02/17/2000|
|    UNIT:  [] [2] []                 STATE:  CA |NOTIFICATION TIME: 10:39[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/16/2000|
+------------------------------------------------+EVENT TIME:        07:59[PST]|
| NRC NOTIFIED BY:  MICHAEL CRAIG                |LAST UPDATE DATE:  03/17/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES MARSCHALL    R4      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| LICENSEE 24-HOUR REPORT DUE TO EXCEEDENCE OF LICENSED POWER LIMIT            |
|                                                                              |
| "On February 16, 2000, at 0759 PST Diablo Canyon Power Plant (DCPP) exceeded |
| the Operating License reactor core power of 3411 megawatts by greater than 2 |
| percent. At 0757 PST with Unit 2 at nominal full reactor power a load        |
| transient bypass (LTB) signal was initiated diverting main feedwater around  |
| the normal feedwater heaters into the steam generators. During the resultant |
| sudden temperature decrease, reactor power peaked at 103.8% and exceeded the |
| nominal full power for a total of six minutes.                               |
|                                                                              |
| "The transient was initiated by utility maintenance personnel during the     |
| scheduled performance of instrumentation calibration of circuits associated  |
| with the LTB. Technicians performing a calibration inadvertently disturbed   |
| an input circuit creating an invalid LTB initiate signal.                    |
|                                                                              |
| "The feedwater temperature was rapidly reduced approximately 45 to 50        |
| degrees F. The Final Safety Analysis Report Update Chapter 15, 'Accident     |
| Analyses,' Condition II, 'Faults of Moderate Frequency,' Section 15.2.11,    |
| 'Sudden Feedwater Temperature Reduction,' provides bounding analysis for     |
| this event. The FSAR Update concludes that for temperature drops of less     |
| than 73 degrees F that the reactor will remain in operation and the reactor  |
| will not go below the minimum DNBR. FSAR Update Section 15.2.11.1 analysis   |
| specifically identifies the inadvertent actuation of the LTB as an           |
| initiating event bound by the analysis.)                                     |
|                                                                              |
| "The DCPP Unit 2 Operating License DPR-82, Condition 2.C(1) authorizes PG&E  |
| to operate Unit 2 at reactor core power levels not in excess of 3411         |
| megawatts thermal (100% rated power). DPR-82, Condition 2.G, 'Reporting,'    |
| requires Emergency Notification System reporting within 24 hours and a       |
| written followup report within 30 day in accordance with the procedures      |
| described in 10 CFR 50.73(b), (c), and (e). This event will be reported as   |
| Licensee Event Report (LER) 2-00-001."                                       |
|                                                                              |
| ************** UPDATE AT 1328 EST ON 03/17/00 FROM RICH LUCKETT TO LEIGH     |
| TROCINE **************                                                       |
|                                                                              |
| The licensee is retracting this event notification because the NRC had       |
| rescinded the requirement to make this report and because the licensee had   |
| not received it.  On 02/24/00, the NRC issued a letter identifying that      |
| Operating License DPR-82, as modified by License Amendment No. 120 on        |
| 02/03/00, was not properly issued to the correct license.  Consequently, the |
| reporting requirement identified was incorrect, and a report was not         |
| required.                                                                    |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R4DO (Graves).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36806       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 03/16/2000|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 18:05[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        03/16/2000|
+------------------------------------------------+EVENT TIME:        14:00[CST]|
| NRC NOTIFIED BY:  ALAN SMITH                   |LAST UPDATE DATE:  03/17/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID GRAVES         R4      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| STATE NOTIFICATION REGARDING A PERSONNEL MEDICAL EMERGENCY                   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Arkansas Nuclear One Unit 1 declared a personnel emergency at 1400 [CST] on |
| 03/16/00 due to a contract employee becoming disoriented while performing a  |
| routine task on top of an overhead crane that is located outside of the      |
| power block.  The individual had performed this task previously without      |
| incident.  The on-site Emergency Medical Team was activated to provide       |
| assistance, and the Pope County Emergency Rescue was requested via 911 to    |
| provide assistance in the safe removal of the individual from the crane.     |
| The individual was subsequently transported to St. Mary's Regional Medical   |
| Center for evaluation via local ambulance service.  The individual was       |
| conscious and in a stable condition following removal from the crane.  This  |
| event may result in news coverage."                                          |
|                                                                              |
| The licensee notified the State and the NRC resident inspector.              |
|                                                                              |
| HOO NOTE:  This report was updated to reflect notification of the State of   |
| Arkansas.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36807       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  THE FOXBORO COMPANY                  |NOTIFICATION DATE: 03/17/2000|
|LICENSEE:  THE FOXBORO COMPANY                  |NOTIFICATION TIME: 09:46[EST]|
|    CITY:  FOXBORO                  REGION:  1  |EVENT DATE:        03/17/2000|
|  COUNTY:                            STATE:  MA |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  03/17/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAURIE PELUSO        R1      |
|                                                |JOHN JACOBSON        R3      |
+------------------------------------------------+VERN HODGE (by fax)  NRR     |
| NRC NOTIFIED BY:  GEORGE JOHNSON               |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 REPORT - LOSS OF GASKET SEAL INTEGRITY ON FOXBORO TRANSMITTER        |
| DISPLAY COVERS                                                               |
|                                                                              |
| The Foxboro Company has identified a potential defect with certain Foxboro   |
| transmitter display covers manufactured between August 1997 and June 1999.   |
| These display covers may not be in compliance with the requirements of leech |
| 1P65 nor NEMA Type-4 Environmental Protection, CENELEC (flameproof), CSA and |
| FM (explosion proof) electrical classification requirements are also         |
| affected.                                                                    |
|                                                                              |
| A Foxboro investigation was initiated upon the return of a commercial grade  |
| display cover which was reported to have lost seal integrity. This           |
| investigation found that an unauthorized manufacturing process change        |
| occurred between August 4, 1997 (date code 9732) and March 12, 1999 (date    |
| code 9911) which allowed an interrupted seal on some portion of the covers   |
| manufactured, compromising the environmental and electrical protection       |
| requirements.                                                                |
|                                                                              |
| Foxboro is taking immediate action to notify all customers who purchased     |
| this product from The Foxboro Company during the time period affected and to |
| provide replacement covers.                                                  |
|                                                                              |
| Indian Point Unit 3 and Cook Units 1 and 2 may be affected by this problem.  |
|                                                                              |
| Foxboro plans to submit a written report to the NRC on this 10 CFR Part 21   |
| Report.                                                                      |
|                                                                              |
| (Call the NRC operations center for contact information.)                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36808       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 03/17/2000|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 14:15[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        03/17/2000|
+------------------------------------------------+EVENT TIME:        10:20[EST]|
| NRC NOTIFIED BY:  GREG PITTS                   |LAST UPDATE DATE:  03/17/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAURIE PELUSO        R1      |
|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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF TWO DIVISION 2 SERVICE WATER SYSTEM (SWP) PUMPS WHILE ONE DIVISION 1 |
| PUMP WAS OUT OF SERVICE                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At time 1020 hours on 03-17-00, Nine Mile Point Unit 2 entered Special      |
| Operating Procedure (SOP) N2-SOP-11 for loss of service water.               |
| Specifically, the Division 2 SWP pumps 2SWP*P1B [and] 2SWP*P1D tripped due   |
| to a low flow condition.  Operations personnel were restoring the Service    |
| Water System (SWP) in accordance with procedure N2-PM-@12, attachment 2, to  |
| align Division 1, following the Division 1 AC electrical bus outage.  A lead |
| was re-landed in the Division 1 SWP logic.  A failed component in this       |
| Division 1 SWP logic caused the safety-related to non-safety-related         |
| isolation valves to isolate.  2SWP*P1C remained in service when the Division |
| 2 pumps tripped.  Subsequently, [the] SWP system was restored to a [one]     |
| pump per division line-up.  Investigation of the failed Division 1 logic     |
| component continues at this time."                                           |
|                                                                              |
| The licensee stated that 2SWP*P1D was restored to service within             |
| approximately 20 minutes and that no fuel moves (as part of a fuel shuffle)  |
| were ongoing at the time of the event.                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36809       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. ARMY                            |NOTIFICATION DATE: 03/17/2000|
|LICENSEE:  U.S. ARMY                            |NOTIFICATION TIME: 15:53[EST]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        03/17/2000|
|  COUNTY:                            STATE:  IL |EVENT TIME:        12:00[CST]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  03/17/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN JACOBSON        R3      |
|                                                |AL BELISLE           R2      |
+------------------------------------------------+DON COOL             NMSS    |
| NRC NOTIFIED BY:  JEFF HAVENNER                |CHARLES MILLER       IRO     |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT AN M43A1 CHEMICAL AGENT DETECTOR CELL MODULE CONTAINING 250   |
| �Ci OF AMERICIUM-241 HAD BEEN MISSING FROM FT. BRAGG (NORTH CAROLINA) SINCE  |
| APRIL 1996                                                                   |
|                                                                              |
| Late yesterday afternoon (03/16/00), representatives from Ft. Bragg, North   |
| Carolina, requested the U.S. Army in Rock Island, Illinois, to help trace    |
| files for documentation regarding a cell module that was discovered to be    |
| missing from an M43A1 chemical agent detector.  (The cell module contained   |
| 250 �Ci of americium-241.)  The most recent documentation found related to   |
| the missing cell module indicated that it was last seen at Ft. Bragg in      |
| April of 1996.  More recent paperwork has not yet been found.  The licensee  |
| determined this event to reportable at approximately 1200 CST today          |
| (03/17/00).                                                                  |
|                                                                              |
| The licensee hypothesized that the M43A1 chemical agent detector may have    |
| been turned into a maintenance unit at some point.  If the device tested     |
| with bad air flow, the maintenance unit could have replaced several items    |
| including the cell module.  At this time, it is believed that the cell       |
| module in question may have been removed (without any paperwork) and that    |
| the device may have been returned without a replacement cell module          |
| installed.                                                                   |
|                                                                              |
| The licensee stated that there does not appear to be any likelihood that the |
| general public will get involved with this issue.  The licensee plans to     |
| submit a 30-day written report to the NRC Region 3 office.                   |
|                                                                              |
| (Call the NRC operations officer for licensee contact information.)          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36810       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 03/17/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 16:52[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/17/2000|
+------------------------------------------------+EVENT TIME:        15:15[CST]|
| NRC NOTIFIED BY:  TERRENCE DORAZIO             |LAST UPDATE DATE:  03/17/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       66       Power Operation  |66       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AS-FOUND TEST VALUES FOR 8 OF 20 MAIN STEAM SAFETY VALVES WERE OUT OF        |
| TOLERANCE HIGH.                                                              |
|                                                                              |
| The preliminary results on the analysis of testing of the main steam safety  |
| valves indicates that the plant was operating outside the design bases.  A   |
| hypothetical turbine trip and loss of load accident would have exceeded the  |
| design limit for secondary side pressure.  The limit for pressure is 1318.5  |
| psig, and preliminary analysis shows a pressure of 1354 psig.  The main      |
| steam safety valves have since been set to within 1% of the tolerance of the |
| required setpoints for all 20 valves.  This action of resetting the valves   |
| returned the plant to within the design basis.                               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36811       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 03/17/2000|
|    UNIT:  [1] [] []                 STATE:  AZ |NOTIFICATION TIME: 20:26[EST]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        03/17/2000|
+------------------------------------------------+EVENT TIME:        17:30[MST]|
| NRC NOTIFIED BY:  BRAD ROBINSON                |LAST UPDATE DATE:  03/18/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID GRAVES         R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF NON-CONSERVATIVE RODDED RADIAL PEAKING FACTORS IN THE CORE      |
| PROTECTION CALCULATORS AND CORE OPERATING LIMIT SUPERVISORY SYSTEM FOR       |
| GROUPS 5 AND P                                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 03/17/00 at approximately 1730 MST, Palo Verde Engineering determined    |
| that Non-conservative Rodded Radial Peaking Factors were installed in the    |
| Unit 1 Core Protection Calculators (CPC) and Core Operating Limit            |
| Supervisory System for Group 5 and Group P.  During the course of normal     |
| operations, Group 5 could be inserted into the core in order to compensate   |
| for Axial Shape Index.  With the current values of Rodded Radial Peaking     |
| Factors, Group 5 may be outside of its design basis.  Control room operators |
| have been briefed on contingency actions to prevent the unit from operating  |
| outside the design basis.  At this time, only Unit 1 is impacted, and the    |
| investigation is continuing."                                                |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
|                                                                              |
| * * *  UPDATE AT 0009 ON 3/18/00, BY BANKS RECEIVED BY WEAVER * * *          |
|                                                                              |
| "On 3/17/00 at 2122, conservative Rodded Radial Peaking Factors were         |
| installed in unit 1, Core Protection Calculators (CPCs channels A, B, & C)   |
| and Core Operating Limit Supervisory System for Group 5 and Group P. CPC     |
| channel D remains out of service for an un-related issue, however, before    |
| the channel is placed back into service, the new conservative Rodded Radial  |
| Peaking Factor will be installed."                                           |
|                                                                              |
| The licensee informed the NRC resident inspector of this update.  The        |
| Operations Center notified the R4DO(Graves).                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36812       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 03/19/2000|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 23:31[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/19/2000|
+------------------------------------------------+EVENT TIME:        20:00[EST]|
| NRC NOTIFIED BY:  MARK SCHALL                  |LAST UPDATE DATE:  03/19/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF REACTOR COOLANT SYSTEM LEAKAGE ON THE WITHDRAWAL LINE WELDS OF  |
| THREE CONTROL ROD DRIVE MECHANISMS DURING HYDRO TESTING                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "EVENT:  During [the performance of procedure] OPT-80. 1, Reactor Pressure   |
| Vessel ASME Vessel ASME Section XI Pressure Test, reactor coolant system     |
| (RCS) pressure boundary leakage was observed on the withdrawal line welds of |
| three control rod drive mechanisms (CRDM).  The following CRDMS were noted   |
| with leakage:  CRDM 06-15 (10 drops/minute at 1030 psig), CRDM 30-15 (20     |
| drops/minute at 1030 psig) and CRDM 14-19 (20 drops/minute at 1030 psig).    |
| This leakage is outside the acceptance standard of zero leakage per ASME     |
| Section XI, Table IWB-3410-1."                                               |
|                                                                              |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION:  Minimal; the leakage is well       |
| within the capacity of available injection systems."                         |
|                                                                              |
| "CORRECTIVE ACTION(S):  The CRDMs will be removed, and the affected areas    |
| repaired prior to reactor startup."                                          |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36813       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 03/20/2000|
|    UNIT:  [] [2] []                 STATE:  SC |NOTIFICATION TIME: 05:02[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/20/2000|
+------------------------------------------------+EVENT TIME:        04:15[EST]|
| NRC NOTIFIED BY:  DON BRADELY                  |LAST UPDATE DATE:  03/20/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(2)(v)      OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE TRANSPORTATION OF A POTENTIALLY CONTAMINATED WORKER                  |
|                                                                              |
| "A vendor support employee was injured due to a fall (approximately 6 to 8   |
| feet) in Unit 2 lower containment.  The individual was supporting reactor    |
| coolant pump work.  Due to injuries, the individual could not be fully       |
| frisked for contamination.  Until further determination, individual is       |
| considered potentially contaminated and is being transported offsite to the  |
| local medical facility."                                                     |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Thursday, March 12, 2020