United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2002

Event Notification Report for September 30, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/27/2002 - 09/30/2002

                              ** EVENT NUMBERS **

39009  39202  39213  39217  39219  39220  39221  39222  39223  39224  39225  39226  39227  39228  39229  39230  

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39009       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  BUREAU OF INDIAN AFFAIRS             |NOTIFICATION DATE: 06/22/2002|
|LICENSEE:  BUREAU OF INDIAN AFFAIRS             |NOTIFICATION TIME: 13:00[EDT]|
|    CITY:  FAIRFAX                  REGION:  4  |EVENT DATE:        06/21/2002|
|  COUNTY:  OSAGE                     STATE:  OK |EVENT TIME:        09:00[CDT]|
|LICENSE#:  35-15239-02           AGREEMENT:  Y  |LAST UPDATE DATE:  09/27/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BOB FAVORS                   |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN TROXLER MOISTURE DENSITY GAUGE                                        |
|                                                                              |
| On 9:00 a.m. CDT on 6/22/02, the licensee discovered that their storage shed |
| had been broken into and a Troxler moisture density gauge was stolen.  The   |
| model number is 3440, which contains 8 millicuries of CS-137 and 40          |
| millicuries of Am-Be 241, and serial numbers 18746 and 18745.  The licensee  |
| contacted the local police, Fairfax City Police and Osage County Sheriffs    |
| office.  The storage shed is located 2 miles east of Highway 20 and Highway  |
| 18 in Osage County, Oklahoma.                                                |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 9/27/02 @ 1528 BY FAVORS TO GOULD * * *                      |
|                                                                              |
| The licensee has recovered the Troxler gauge.  It was returned to them       |
| undamaged with the source lock intact by the Fairfax, Ok. Police Dept. on    |
| 9/25/02.                                                                     |
|                                                                              |
| HOO notified MNSS EO(Brown) and REG 4 RDO(Pellet)                            |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39202       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 09/20/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 04:12[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/20/2002|
+------------------------------------------------+EVENT TIME:        01:12[EDT]|
| NRC NOTIFIED BY:  TIM JOHNSON                  |LAST UPDATE DATE:  09/27/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT ACTUATION OF BLACKOUT SIGNAL ON UNIT 1 DURING SURVEILLANCE       |
| TESTING                                                                      |
|                                                                              |
| "Inadvertent Actuation of B Train Blackout Signal on Unit 1. Actuation       |
| occurred during testing of the 1B Diesel Generator sequence panel. The       |
| actuation caused the B Train Nuclear Service Water System to realign to the  |
| standby Nuclear Service Water Pond on both Unit 1 and Unit 2. Unit 2 was not |
| affected due to the realignment. The Unit 1 Boric Acid pump transfer pump    |
| automatically secured and various containment and Auxiliary Building         |
| Ventilation components were affected due to the actuation. The procedure     |
| used for testing the sequencer simulated an undervoltage signal on the B     |
| Train Emergency Bus. Plans are being evaluated to restore the sequencer from |
| the test alignment and realign all affected equipment."                      |
|                                                                              |
| Neither reactor residual heat removal cooling or spent fuel pool cooling     |
| were affected by this event.  Electrical buses remained energized and no EDG |
| autostart occurred since the blackout signal was simulated and not based on  |
| an actual undervoltage condition.  The licensee is attributing the cause     |
| preliminarily to an inadequate procedure.                                    |
|                                                                              |
| The licensee will notify the NRC Resident Inspector.                         |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 9/27/02 @ 1437 BY JOHNSON TO GOULD * * *       RETRACTION    |
|                                                                              |
| Further evaluation determined that the blackout signal which automatically   |
| aligned RN to the SNSWP was not in response to actual plant conditions or    |
| parameters satisfying the requirements for initiation of a blackout signal   |
| or the SNSWP safety function. Since alignment of RN to the SNSWP was not in  |
| response to a valid signal, this represented an invalid actuation which is   |
| not reportable per 10 CER 50.72(b) (3) (iv) (A).   In addition, 10 CFR       |
| 50.72(b) (3) (iv) (B) does not identify the ultimate heat sink portion of RN |
| systems as a system applicable to 10 CFR 50.72(b) (3) (iv) (A). Therefore,   |
| McGuire is retracting Event Report 39202.                                    |
|                                                                              |
| Note: McGuire will report this event in accordance with the requirements of  |
| 10 CFR 50.73. (see event # 39223)                                            |
|                                                                              |
| The licensee will notify the NRC Resident Inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39213       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OR DEPT OF HEALTH RAD PROTECTION     |NOTIFICATION DATE: 09/24/2002|
|LICENSEE:  GEOPACIFIC TESTING                   |NOTIFICATION TIME: 11:43[EDT]|
|    CITY:                           REGION:  4  |EVENT DATE:        09/23/2002|
|  COUNTY:                            STATE:  OR |EVENT TIME:             [PDT]|
|LICENSE#:  ORE-90987             AGREEMENT:  Y  |LAST UPDATE DATE:  09/24/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |DOUG BROADDUS        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY LINDSEY                |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MOISTURE DENSITY GAUGE LOST DURING TRANSPORT                                 |
|                                                                              |
| A Troxler gauge, model # 3440, serial # 19495 was lost while being           |
| transported from Beverton, OR to North Portland, OR. The gauge is an 8       |
| millicurie Cs-137, 40 millicurie Am-Be 241 source and is licensed to         |
| GeoPacific Testing Inc, Tigard, OR 97224. The licensee discovered the lost   |
| gauge on 9/23/02 at approximately 1700 PDT and notified the State of Oregon  |
| on 9/23/02 at 1858 PDT. The gauge was lost north of Highway 26 between the   |
| intersection of Emily Lane and Northwest Bethany Blvd and Northwest          |
| Germantown Rd.  A search is being conducted to recover the lost gauge. A     |
| press release is planned. The Oregon State Police, Oregon Emergency Response |
| System, Washington County Sheriff, Beaverton Police and the Portland Police  |
| have been notified. The State of Oregon also intends to notify NRC Region    |
| 4.                                                                           |
|                                                                              |
| * * * UPDATE ON 9/24/02 AT 2138 EDT FROM TERRY LINDSEY TO GERRY WAIG * * *   |
|                                                                              |
| The Troxler moisture density gauge lost during transit was discovered by a   |
| passing volunteer fireman from Scapoose, OR. The fireman happened by the     |
| gauge, picked up the gauge and case, and secured it at the fire house. The   |
| gauge was found on 185th Ave., along the original route traveled when lost,  |
| approximately 15 minutes after it was lost.  The gauge was reported found    |
| after news of the missing gauge was aired today on local media. The gauge is |
| currently being stored by the Scapoose Fire Dept. and will be returned to    |
| GeoPacific Testing tomorrow.                                                 |
|                                                                              |
| Notified R4DO (John Pellet) and NMSS (John Greeves)                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39217       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 09/26/2002|
|LICENSEE:  CONSTRUCTION TESTING AND ENGINEERING,|NOTIFICATION TIME: 00:26[EDT]|
|    CITY:                           REGION:  4  |EVENT DATE:        09/24/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:        07:30[PDT]|
|LICENSE#:  CA 5309-37            AGREEMENT:  Y  |LAST UPDATE DATE:  09/26/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:                               |                             |
|  HQ OPS OFFICER:                               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:                                |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN AND RECOVERED MOISTURE DENSITY GAUGE                                  |
|                                                                              |
| "The facility [Construction Testing and Engineering, Inc.] reported a stolen |
| gauge this morning and within an hour called back to report that the gauge   |
| had been recovered [by police].                                              |
|                                                                              |
| "The gauge had been picked up from the storage location around 4:30 AM that  |
| morning and was transported by the user to his home. The gauge remained      |
| locked by chain in the vehicle. When the user returned to his vehicle        |
| between 7:30 - 8 AM he discovered the chain had been cut and the case with   |
| the gauge was missing. He contacted the police and the Alternate Radiation   |
| Safety Officer for his region."                                              |
|                                                                              |
| CA Rad Health Branch will follow-up with the licensee to obtain the make,    |
| model, and serial number of the stolen/recovered gauge and will forward that |
| information to the Headquarters Operations Officer.                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39219       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ARCTIC PIPE INPSECTIONS              |NOTIFICATION DATE: 09/26/2002|
|LICENSEE:  ARCTIC PIPE INSPECTIONS              |NOTIFICATION TIME: 17:06[EDT]|
|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        09/26/2002|
|  COUNTY:                            STATE:  TX |EVENT TIME:        09:00[CDT]|
|LICENSE#:  50-17314-02           AGREEMENT:  Y  |LAST UPDATE DATE:  09/27/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+ANIELLO DELLA GRECA  R1      |
| NRC NOTIFIED BY:  JIM HILDEBRENDT              |RICHARD WESSMAN      IRO     |
|  HQ OPS OFFICER:  MIKE NORRIS                  |JOHN DAVIDSON        NSIR    |
+------------------------------------------------+DWIGHT CHAMBERLAND   R4      |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST I-192 RADIOGRAPHY SOURCE DURING SHIPMENT                                |
|                                                                              |
| A 20.3 Curie Ir-192 radiography camera SN# 94 was being shipped from Kenin,  |
| AK to AEA Technologies in Burlington, MA by Federal Express.  The shipment   |
| arrived in Newark, NJ on 9/21/02 at 0257 and was scanned to leave on 9/24/02 |
| at 0022 EDT.  The Licensee reported that the camera has not arrived in MA,   |
| and that Federal Express could not account for the source's location.  The   |
| source was being shipped in it's shipping container and the Licensee         |
| believed that it had a combination lock on it.                               |
|                                                                              |
| ***UPDATE CHUCK CAIN TO MIKE NORRIS 1800 9/27/02***                          |
|                                                                              |
| The missing Arctic Pipe source changer has been found at the FedEx Newark    |
| terminal.  The shipping container was not damaged, but had it's paperwork    |
| missing.  Notified R4DO (Pellet), R1DO (Della Greca), DIRO (Wessman), NSIR   |
| IAT (Davidson) and OHS (Brahm).                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39220       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 09/27/2002|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 09:11[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/27/2002|
+------------------------------------------------+EVENT TIME:        08:50[EDT]|
| NRC NOTIFIED BY:  RICK O'REARS                 |LAST UPDATE DATE:  09/28/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |MICHAEL JOHNSON      NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |RICHARD WESSMAN      IRO     |
|                                                |DAN SULLIVAN         FEMA    |
|                                                |DAVE ANDERSON        OHS     |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| NOUE DECLARED DUE TO LOSS OF OFFSITE POWER SUPPLY                            |
|                                                                              |
| The licensee declared a notice of unusual event (NOUE),in accordance with    |
| EAL 3.1, due to the loss of two offsite electrical power supplies to the     |
| station for greater than 15 minutes. The cause of the loss of offsite power  |
| was a fire at a local hydro electric station. All systems functioned as      |
| required. All emergency diesels responded and supplied electrical power to   |
| the station shutdown electrical boards. The loss of two offsite power        |
| supplies places the station in a technical specification (TS 3.8.1 D)        |
| limiting condition for operation (LCO).                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector, the State of Tennessee,    |
| and the local fire department.                                               |
|                                                                              |
| At 0955 NRC entered Monitoring for Normal Phase Mode.                        |
|                                                                              |
| * * * UPDATE ON 09/28/02 AT 0311 FROM RICKY STOCKTON TO GERRY WAIG * * *     |
|                                                                              |
| The licensee terminated the NOUE at 0308 after the second offsite electrical |
| power supply was restored to the site at 0300 and exited technical           |
| specifications 3.8.1 limiting conditions for operation. The first offsite    |
| power supply was restored at 0125.                                           |
|                                                                              |
| At 0311 NRC exited monitoring for the Unusual Event                          |
|                                                                              |
| Notified IRO (Wessman), R2DO (W. Rogers ), PAO (R. Virgilio ), NRR EO (M.    |
| Johnson), FEMA (K.C.), OHA Ron Brahm                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39221       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 09/27/2002|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 11:01[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/27/2002|
+------------------------------------------------+EVENT TIME:        10:40[EDT]|
| NRC NOTIFIED BY:  PAUL PACE                    |LAST UPDATE DATE:  09/27/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |MICHAEL JOHNSON      NRR     |
|ADEV 50.72(b)(1)         DEVIATION FROM T SPEC  |RICHARD WESSMAN      IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| DEVIATION FROM TECHNICAL SPECIFICATIONS PER 10 CFR 50.54(x)                  |
|                                                                              |
| The licensee reported a deviation from license condition 2 F, which requires |
| compliance with the Watts Bar Fire Protection Report, part 2, section 9.1,   |
| per 10 CFR 50.54(x). This section requires the minimum fire brigade staffing |
| to be restored within two hours. The Watts Bar fire brigade was dispatched   |
| to a fire at the nearby Watts Bar Hydro Generation Station (see NRC Event    |
| Number 39220) and replacement fire brigade members had not yet arrived       |
| on-site.  The licensee stated that the fire brigade can respond to a fire at |
| Watts Bar Nuclear but response time would be greater than normal.            |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39222       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GLOBAL NUCLEAR FUEL - AMERICAS       |NOTIFICATION DATE: 09/27/2002|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 11:04[EDT]|
| COMMENTS: LEU CONVERSION (UF6 TO UO2)          |EVENT DATE:        09/27/2002|
|           LEU FABRICATION                      |EVENT TIME:        07:30[EDT]|
|           LWR COMMERICAL FUEL                  |LAST UPDATE DATE:  09/27/2002|
|    CITY:  WILMINGTON               REGION:  2  +-----------------------------+
|  COUNTY:  NEW HANOVER               STATE:  NC |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1097              AGREEMENT:  Y  |WALTER RODGERS       R2      |
|  DOCKET:  07001113                             |TOM ESSIG            NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PAULSON                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FOUR HOUR 91-01 BULLETIN RESPONSE                                            |
|                                                                              |
| At approximately 7:30 a.m. on September 27, 2002, a UO2 furnace operator     |
| reported an overload alarm condition at the Line 1 UO2 sintering furnace.    |
| Subsequent visual inspection of the furnace indicated a pellet boat "jam"    |
| had occurred inside the sintering furnace chamber.   An estimated 4-5 boats  |
| are involved in the localized area in which the jam occurred. The stacking   |
| of the boats inside the furnace constitutes a loss of geometry control.      |
|                                                                              |
| The independent control on moderation remained intact, thus no unsafe        |
| condition existed, or currently exists.  The UO2 sintering furnace           |
| temperature is in excess of 1700 degrees C.                                  |
|                                                                              |
| Following procedure, operations promptly notified nuclear safety.  Safe      |
| recovery of the material and re-establishment of the geometry control will   |
| require a 2 week cool down.  This condition is reported pursuant to NRC      |
| bulletin 91-01 (within 4 hours) due to a loss of geometry that requires in   |
| excess of 4 hours to re-establish.  Implementation of corrective actions is  |
| pending completion of incident investigation,                                |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
| Low safety significance - localized loss of safe slab geometry, moderation   |
| control remained intact.                                                     |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW            |
| CRITICALITY COULD OCCUR):                                                    |
| Multiple failure modes required before a criticality accident could occur.   |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):     |
| Geometry and moderation.                                                     |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST BASE CRITICAL MASS):                                       |
|                                                                              |
| Estimated 4-5 pellet boats involved in actual  jam  represent [ . . .] kgs   |
| UO2 in the form of dry fuel pellets, enriched to [ . . . ]                   |
|                                                                              |
| wt% U235. Under a loss of geometry, our analyses have demonstrated a fully   |
| reflected hemisphere mass of UO2 pellets at [ . . . ] enrichment containing  |
| 5% water is ~[. . . ]kgs. Thus, a large safety margin exists for this loss   |
| of geometry Condition.                                                       |
|                                                                              |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES:                                             |
| The geometry control provided by safe slab height of 3  was lost because of  |
| jam  inside UO2 sintering furnace.                                           |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
| Controlled shutdown of sintering furnace (requires 2 weeks to cool down),    |
| recovery of material into favorable geometry containers under NSE approved   |
| procedure.                                                                   |
|                                                                              |
|                                                                              |
| Investigation of event and evaluation of additional corrective actions       |
| pending.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39223       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 09/27/2002|
|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 14:37[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/20/2002|
+------------------------------------------------+EVENT TIME:        01:12[EDT]|
| NRC NOTIFIED BY:  JOHNSON                      |LAST UPDATE DATE:  09/27/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT ALIGNMENT OF THE NUCLEAR SERVICE WATER TO STANDBY NUCLEAR        |
| SERVICE WATER POND                                                           |
|                                                                              |
| On September 20, 2002, McGuire Nuclear Station experienced an inadvertent    |
| alignment of the Nuclear Service Water (EN) system to the Standby Nuclear    |
| Service Water Pond (SNSWP).  This event occurred when a Unit 1 "B" Train     |
| blackout signal was inadvertently generated during surveillance testing of   |
| the 13 Diesel Generator sequencer panel.                                     |
|                                                                              |
| Further evaluation determined that the blackout signal which automatically   |
| aligned RN to the SNSWP was not in response to actual plant conditions or    |
| parameters satisfying the requirements for initiation of a blackout signal   |
| or the SNSWP safety function.  Since alignment of RN to the SNSWP was not in |
| response to a valid signal, this represented an invalid actuation reportable |
| per the requirements of 10 CFR 50.73(a)(2)(iv)(A).  However, as per 10 CFR   |
| 50.73(a) (1), McGuire is providing a telephone notification of this invalid  |
| actuation instead of submitting a written LER.                               |
|                                                                              |
| The following additional information is being provided as part of the        |
| telephone notification of this event:                                        |
|                                                                              |
| "B" Train of RN actuated to align Unit 1 and Unit 2 RN to the SNSWP.         |
|                                                                              |
| "B" Train actuation of Unit 1 and 2 RN to the SNSWP functioned successfully  |
| and was complete.                                                            |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39224       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 09/27/2002|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 15:58[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/27/2002|
+------------------------------------------------+EVENT TIME:        08:24[EDT]|
| NRC NOTIFIED BY:  PAUL PACE                    |LAST UPDATE DATE:  09/27/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| VALID ENGINEERED SAFETY FUNCTION ACTUATION DUE TO PARTIAL LOSS OF OFF SITE   |
| POWER                                                                        |
|                                                                              |
| "While operating at 100% power on September 27, 2002, Watts Bar experienced  |
| a loss of one off-site power source, followed about 15 minutes later by the  |
| loss of the second off-site power source.  These two off-site power sources  |
| are fed from the Watts Bar Hydro plant, and are the primary power source for |
| the 6900 V shutdown boards, via Common Station Service Transformers (CSST's) |
| C & D.  CSST C feeds shutdown bds[boards] 1A-A & 2A-A, CSST D feeds shutdown |
| bds 1B-B & 2B-B.  A fire at the hydo plant was the cause of the off-site     |
| power supply breakers opening.  The breaker for the supply to the CSST C     |
| opened at 0824 (EDT).  This deenergized shutdown bds 1A-A & 2A-A, initiating |
| a valid engineered safety function (ESF) actuation that started all four     |
| standby diesel generators (DG's), two of which reenergized these shutdown    |
| bds.  When the other off-site source was lost, the remaining 2 DG's then     |
| loaded onto their respective shutdown bds.  The plant remain at full power   |
| since one train of shutdown power was always available.  As designed, AFW    |
| started coincident with the EDG start.  At this time, the 2 lines have been  |
| reenergized and the A, B, C and D Common Station Service Transformers are    |
| also energized.  Preparations are being made to re-power nonsafety related   |
| loads from off-site power."                                                  |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39225       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 09/27/2002|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 17:00[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        09/16/2002|
+------------------------------------------------+EVENT TIME:        16:15[EDT]|
| NRC NOTIFIED BY:  BEACH                        |LAST UPDATE DATE:  09/27/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANIELLO DELLA GRECA  R1      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INVALID PRIMARY CONTAINMENT ISOLATION OF GROUP 2 AND 3 OUTBOARD VALVES       |
|                                                                              |
|                                                                              |
| This 60-day optional report, as allowed by 10 CFR 50.73(a)(1), is being made |
| under the reporting requirement in                                           |
| 10CFR50.73(a)(2)(iv)(A) to describe an unplanned, invalid actuation of a     |
| specified system, specifically Primary                                       |
| Containment Isolation Valve (PCIV) Group 2 and 3 outboard valves.            |
|                                                                              |
| On September 16, 2002, an over-voltage on the power supply to "B" Reactor    |
| Protection System (RPS) bus resulted                                         |
| in a loss of power to the bus.  The loss of power resulted in an invalid     |
| isolation of the outboard Secondary Containment Isolation Valves (SCIV) and  |
| outboard Group 2 and 3 PCIVs. Additionally, "B" Standby Gas Treatment (SGT)  |
| started due to an invalid auto initiation signal and RPS received an invalid |
| half scram signal.                                                           |
|                                                                              |
| The affected systems responded as expected for the given conditions and were |
| subsequently returned to a normal configuration when power was restored to   |
| the  B  RPS bus. No deficiencies or abnormalities were noted during the      |
| event.                                                                       |
|                                                                              |
| This event has been entered into the site-specific corrective action program |
| for resolution.                                                              |
|                                                                              |
| The NRC resident has been informed.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39226       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 09/27/2002|
|    UNIT:  [1] [2] [3]               STATE:  AZ |NOTIFICATION TIME: 18:52[EDT]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        09/27/2002|
+------------------------------------------------+EVENT TIME:        15:00[MST]|
| NRC NOTIFIED BY:  STROUD                       |LAST UPDATE DATE:  09/27/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       99       Power Operation  |99       Power Operation  |
|2     N          Y       99       Power Operation  |99       Power Operation  |
|3     N          Y       99       Power Operation  |99       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFF-SITE NOTIFICATION                                                        |
|                                                                              |
| On September 27, 2002 at approximately 15:00 Mountain Standard Time, Palo    |
| Verde Nuclear Generating Station                                             |
| (PVNGS) notified the Environmental Protection Agency (EPA) that a INITIAL    |
| NOTIFICATION OF CONTINUOUS RELEASE was being reported.                       |
|                                                                              |
| The following information was provided to the National Response Center and   |
| State of Arizona:                                                            |
|                                                                              |
| "Palo Verde Nuclear Generating Station is calling to make an initial         |
| notification of a continuous release in accordance                           |
| with CERCLA Section 103(f)(2). 40CFR 302.8 (d).  This is not an accidental   |
| or episodic release.                                                         |
|                                                                              |
| Palo Verde Nuclear Generating Station will be performing a scheduled steam   |
| generator cleaning activity as part of its routine refueling outage for Unit |
| 1.  The steam generator cleaning activity will begin on Saturday, September  |
| 28 at                                                                        |
| approximately 18:00.  During this activity, Palo Verde Nuclear Generating    |
| Station will exceed the Reportable Quantities for the release of ammonia and |
| hydrazine.  The same activity is scheduled to occur during the Unit 3        |
| refueling outage, spring of 2003.  The activity occurs approximately once    |
| per every five to seven years on each unit.  The hazardous substances        |
| released are ammonia (CAS #7684-41-7) and hydrazine (GAS #302-01-2).  PVNGS  |
| expects no adverse effects to health and welfare of the general public, nor  |
| to the environment.                                                          |
|                                                                              |
| The NRC Resident Inspector was notified along with the State.                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39227       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON                    REGION:  3  |NOTIFICATION DATE: 09/28/2002|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 15:36[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/28/2002|
+------------------------------------------------+EVENT TIME:        13:45[CDT]|
| NRC NOTIFIED BY:  PRINTZ                       |LAST UPDATE DATE:  09/28/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KENNETH RIEMER       R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71(b)(1)         SAFEGUARDS REPORTS     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY                                    |
|                                                                              |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY                         |
|                                                                              |
| CONTACT HOO FOR ADDITIONAL DETAILS                                           |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS INFORMED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39228       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 09/28/2002|
|    UNIT:  [1] [2] [3]               STATE:  AZ |NOTIFICATION TIME: 20:45[EDT]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        09/28/2002|
+------------------------------------------------+EVENT TIME:        14:10[MST]|
| NRC NOTIFIED BY:  DON STRAKA                   |LAST UPDATE DATE:  09/28/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|2     N          Y       99       Power Operation  |99       Power Operation  |
|3     N          Y       99       Power Operation  |99       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SPURIOUS ACTUATION OF ONE OFFSITE EP SIREN                                   |
|                                                                              |
| "At 14:10 on 09128/2002, the Palo Verde Unit 1 Control Room was notified of  |
| a spurious actuation of one siren. The siren is located near Southern and    |
| Palo Verde Roads. This siren provides emergency notification to              |
| approximately 39 Members of the Public.                                      |
|                                                                              |
| "No press release is planned at this time, however, the event is being       |
| reported due to inquiries from the Maricopa                                  |
| County Department of Emergency Management to troubleshoot the siren and      |
| notification of the siren actuation to the                                   |
| Maricopa County Sheriffs Office.                                             |
|                                                                              |
| "Personnel have been dispatched to turn off the siren.                       |
|                                                                              |
| "There is no event in progress and no risk to the health and safety of the   |
| public. Members of the public within audible                                 |
| range of the siren may have a concern for their radiological health and      |
| safety.                                                                      |
|                                                                              |
| "Unit 1 is at approximately 0% power In Mode 5 at the start of its scheduled |
| refueling outage. Unit 2 is at approximately 99% power in Mode 1 at normal   |
| operating temperature and pressure. Unit 3 is at approximately 99% power in  |
| Mode 1 at normal operating temperature and pressure.                         |
|                                                                              |
| "The NRC Resident Inspector has been informed of the siren actuation and     |
| this ENS notification. Note: The checkbox  for OTHER GOV AGENCIES is         |
| referring to the Maricopa County agencies discussed above."                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39229       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 09/29/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 13:11[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/29/2002|
+------------------------------------------------+EVENT TIME:        05:02[EDT]|
| NRC NOTIFIED BY:  HOFFMAN                      |LAST UPDATE DATE:  09/29/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP SIGNAL DUE TO LOW-LOW STEAM GENERATOR LEVEL.                    |
|                                                                              |
| While draining the 1"D" steam generator, a reactor trip signal was generated |
| due to a low-low steam generator level.  One train of the reactor protection |
| system was being tested, so one trip breaker opened in response to the trip  |
| signal.  The low-low steam generator level was due to a planned evolution    |
| and was a valid signal.  There was no safety significance because all        |
| control rods were already inserted into the fuel assemblies, the control     |
| rods were not latched to the control rod drive system, and the motor         |
| generator sets were shutdown by procedure.  Although the reactor trip        |
| breaker was closed during testing, at no point was control rod withdrawal    |
| possible.  They are investigating the cause.                                 |
|                                                                              |
| The NRC Resident Inspector will be notified                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39230       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 09/29/2002|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 20:20[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        09/10/2022|
+------------------------------------------------+EVENT TIME:        17:32[EDT]|
| NRC NOTIFIED BY:  PETE SENA                    |LAST UPDATE DATE:  09/29/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANIELLO DELLA GRECA  R1      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT START OF A STANDBY SERVICE WATER PUMP DURING RESTORATION FROM A  |
| CALIBRATION ACTIVITY                                                         |
|                                                                              |
| "On September 10, 2002 at 1732 hrs, a pressure transmitter in the Service    |
| Water System was being returned to service after the performance of an       |
| instrument calibration procedure. The transmitter was being vented in order  |
| to return the transmitter to service. During the venting evolution, an       |
| inadvertent start of 2SWE-P21B, B Standby Service Water Pump, occurred. The  |
| pump start was due to low pressure as seen by a second transmitter, which    |
| shares a common sensing line with the transmitter that was being vented.     |
| This second transmitter provides an input to the auto start feature for the  |
| B Standby Service Water Pump. Venting the transmitter caused low pressure in |
| the common sensing line which activated the auto start feature. Since the    |
| low pressure was only seen locally at the transmitter and not throughout the |
| system, this was an invalid actuation. Low service water system header       |
| pressure is the parameter which would activate this feature and low service  |
| water system header pressure was not experienced during this event. A        |
| complete actuation of the B train of the Standby Service Water System        |
| occurred and the system functioned properly.                                 |
|                                                                              |
| "This event is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) since it     |
| involved an automatic actuation of an emergency service water system that    |
| does not normally run and that serves as an ultimate heat sink as per 10 CFR |
| 50.73(a)(2)(iv)(B)(9). This actuation was not part of a pre-planned sequence |
| and did not occur with this system properly removed from service.            |
|                                                                              |
| "However, pursuant to 10 CFR 50.73(a)(1), this event is being reported via   |
| this telephone notification instead of submitting a written Licensee Event   |
| Report since the automatic actuation of the Standby Service Water pump was   |
| not generated by a valid actuation."                                         |
|                                                                              |
| The NRC Resident was notified.                                               |
+------------------------------------------------------------------------------+