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Event Notification Report for May 4, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/03/2001 - 05/04/2001

                              ** EVENT NUMBERS **

37962  37963  37964  

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|Power Reactor                                    |Event Number:   37962       |
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| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 05/03/2001|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 09:54[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/03/2001|
+------------------------------------------------+EVENT TIME:        07:00[EDT]|
| NRC NOTIFIED BY:  A. WISNIEWSKI                |LAST UPDATE DATE:  05/03/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |HAROLD GRAY          R1      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| LOCAL LEAK RATE FAILED                                                       |
|                                                                              |
| At 0700, on 05/03/01, the Control Room was informed that the HPCI Steam      |
| Exhaust Check Valves, V23-3 & V23-4, failed their local leak rate test such  |
| that the minimum pathway leakage rate was exceeded, greater than 193.674     |
| scfh which is in excess of 0.6La Tech Spec limit.   The valves were declared |
| inoperable and repairs are underway.                                         |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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|Power Reactor                                    |Event Number:   37963       |
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| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 05/03/2001|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 13:36[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/12/2001|
+------------------------------------------------+EVENT TIME:        00:30[EDT]|
| NRC NOTIFIED BY:  KEN RUSSELL                  |LAST UPDATE DATE:  05/03/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|*INV 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        Refueling        |0        Startup          |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| ACTUATION OF DIVISION 1 BALANCE-OF-PLANT OUTBOARD ISOLATION VALVES - INVALID |
| SYSTEM ACTUATION                                                             |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On March 12, 2001, at approximately 0030 hours, the Perry Nuclear Power     |
| Plant experienced an actuation of Division 1 Balance-of-Plant (BOP) outboard |
| isolation valves.  At the time of the event, the plant was in Mode 5         |
| (Refueling), and had been subcritical for approximately 23 days.  The        |
| reactor pressure vessel (RPV) head was removed and the refuel cavity and     |
| upper containment pools were flooded; no core alterations were in progress   |
| at the time.  Shutdown cooling was being provided by the Fuel Pool Cooling   |
| and Clean-up system (FPCC), which was aligned to the upper containment pool. |
| The isolation signal closed one or more valves in each of the following      |
| Division 1 subsystems:  FPCC, Containment Drywell purge, Two-Bed             |
| Demineralized Water System, Fire Protection, Liquid Radwaste Sumps, Liquid   |
| Radwaste Disposal, Instrument Air, Containment Vessel Chilled Water,         |
| Condensate Transfer and Storage.  In addition, the isolation signal caused a |
| temporary interruption of shutdown cooling flow through the FPCC system,     |
| until it was re-established by on-shift Operations personnel."               |
|                                                                              |
| "The event is considered an invalid system actuation, and is reportable      |
| under 10 CFR 50.73(a)(2)(iv)(A).  The isolation was not initiated in         |
| response to actual plant conditions or parameters, and was not a manual      |
| initiation.  It meets the criteria specified in 10 CFR 50.73(a)(2)(iv)(B)(2) |
| as a general containment isolation signal affecting containment isolation    |
| valves in more than one system.  Therefore, notification is being provided   |
| via 60-day optional phone call in accordance with 10 CFR 50.73(a)(1).  All   |
| systems functioned as expected for a partial BOP (outboard) isolation."      |
|                                                                              |
| "The interruption of shutdown cooling lasted for 111 minutes, from 0030      |
| hours to 0221 hours on March 12, 2001.  During this time, the reactor water  |
| temperature increased approximately 3 degrees, from 99 to 102 degrees.  The  |
| estimated time to boil was conservatively calculated at 28 hours.  The       |
| affected Fire Protection (drywell CO2) isolation valve was not required to   |
| be open, since the fire-protected equipment was secured during the refueling |
| outage.  Repositioning of the other valves did not present operational       |
| concerns; they were re-opened per restoration procedures.  The cooling flow  |
| path was available immediately with manual operator action."                 |
|                                                                              |
| "The BOP isolation was attributed to scheduled maintenance activities being  |
| conducted in the Control Room.  The replacement of a bayonet-socket-style    |
| relay caused two fuses to blow in the BOP manual initiation logic circuit.   |
| The apparent cause was an inadvertent ground from the seismic strap of the   |
| new relay during installation that resulted in the required logic for the    |
| isolation."                                                                  |
|                                                                              |
| "This event was documented in the Corrective Action Program.  Remedial       |
| actions include review of the event with instrumentation and control         |
| technicians, and evaluation of depowering valves which could interrupt       |
| shutdown cooling during maintenance activities."                             |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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|Other Nuclear Material                           |Event Number:   37964       |
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| REP ORG:  3M COMPANY                           |NOTIFICATION DATE: 05/03/2001|
|LICENSEE:  W. L. GORE                           |NOTIFICATION TIME: 14:06[EDT]|
|    CITY:  EAUCLAIRE                REGION:  3  |EVENT DATE:        10/22/2000|
|  COUNTY:                            STATE:  WI |EVENT TIME:             [CDT]|
|LICENSE#:  1429-1811GL           AGREEMENT:  N  |LAST UPDATE DATE:  05/03/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MELVYN LEACH         R3      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+DICK WESSMAN         IRO     |
| NRC NOTIFIED BY:  MIKE LEWANDOWSKI             |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 3M COMPANY REPORT REGARDING A W. L. GORE FACILITY LOSS OF A STATIC           |
| ELIMINATOR CONTAINING 10 MILLICURIES OF POLONIUM-210                         |
|                                                                              |
| On 09/12/00, 3M Company (located in St. Paul, Minnesota) announced its       |
| intent to purchase W. L. Gore (located in Eauclaire, Wisconsin).  The        |
| acquisition took place during late October or early November 2000.  On       |
| 03/14/01, 3M Company representatives visited the newly acquired W. L. Gore   |
| facility and discovered the existence of static eliminators.  An audit was   |
| subsequently performed, and 3M Company was able to account for all but one   |
| static eliminator.                                                           |
|                                                                              |
| Apparently, the W. L. Gore facility received the polonium static eliminator  |
| in question on 08/10/00.  This static eliminator was manufactured by Nuclear |
| Radiation Development (NRD), and it was comprised of an in-line ionizer tube |
| approximately 4 inches long and 1/4 inch in diameter with 10 millicuries of  |
| polonium-210 plated on the inside of the device.  The static eliminator was  |
| installed on a large circuit substrate manufacturing machine for use in the  |
| W. L. Gore facility under the NRD general license (1429-1811GL).             |
|                                                                              |
| On 09/06/00, the circuit substrate manufacturing machine was sent back to    |
| its manufacturer (Everrett Charles) for an upgrade.  The static eliminator   |
| was reported to be on the machine when it was shipped to Everrett Charles    |
| (location unknown); however, the static eliminator was determined to be      |
| missing after Everrett Charles returned the upgraded machine to W. L. Gore   |
| on 10/22/00.                                                                 |
|                                                                              |
| Everrett Charles was notified of the missing static eliminator during the    |
| week of 04/09/01.  NRD was also notified during the week of 04/16/01.  It    |
| was reported that searches were performed, but the missing static eliminator |
| was not found.                                                               |
|                                                                              |
| (Call the NRC operations officer for a 3M Company contact telephone number.) |
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