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Event Notification Report for November 5, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/04/1999 - 11/05/1999

                              ** EVENT NUMBERS **

35790  36263  36394  36395  36396  36397  36398  36399  36400  36401  

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|Fuel Cycle Facility                              |Event Number:   35790       |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/03/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/02/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:30[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/04/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |DAVID HILLS          R3      |
|  DOCKET:  0707001                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  THOMAS WHITE                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| THREE SPRINKLER SYSTEMS DECLARED INOPERABLE DUE TO CORRODED HEADS (24-hour   |
| report)                                                                      |
|                                                                              |
| "On 06/02/99 at 1630 CDT, the Plant Shift Superintendent (PSS) was notified  |
| that numerous sprinkler heads were corroded, affecting 16 sprinkler systems  |
| in C-337 and one system in C-333, such that the ability of the sprinklers to |
| flow sufficient water was called into question.  Subsequently, these         |
| sprinkler systems were declared inoperable, and TSR-required actions         |
| establishing roving fire patrols were initiated.  This deficiency was        |
| detected during scheduled system inspections conducted by Fire Protection    |
| personnel.  Currently, functionality of the sprinkler heads has not been     |
| fully evaluated by Fire Protection personnel, and the remaining cascade      |
| buildings are currently being inspected, and if necessary, this report will  |
| be updated to identify any additional areas.  It has been determined that    |
| this event is reportable under 10CFR76.120(c)(2) as an event in which        |
| equipment is disabled or fails to function as designed."  The NRC resident   |
| inspector has been notified of this event.                                   |
|                                                                              |
| * * * UPDATE AT 1022 EDT ON 06/04/99 FROM CAGE TO TROCINE * * *              |
|                                                                              |
| "Two sprinkler heads on system D-1 in C-337 and two sprinkler heads on       |
| system 27 in C-335 were identified to also be corroded.  These were          |
| identified to the PSS on 06/03/99 at 1600 CDT and 1601 CDT, respectively,    |
| and determined to require an update to this report by the PSS.  It has been  |
| determined that this event is reportable under 10CFR76.120(c)(2) as an event |
| in which equipment is disabled or fails to function as designed."  Paducah   |
| personnel notified the NRC resident inspector of this update.  The NRC       |
| operations officer notified the R3DO (Hills) and NMSS EO (Combs).            |
|                                                                              |
| * * * UPDATE AT 2152 EDT ON 06/17/99 FROM WALKER TO POERTNER * * *           |
|                                                                              |
| "Three sprinkler heads on system C-15 and five sprinkler heads on system B-8 |
| in C-333 were identified to also be corroded.  The PSS was notified of this  |
| condition at 1300 CDT on 06/17/99 and determined that an update to this      |
| report was required.  It has been determined that this event is reportable   |
| under 10CFR76.120(c)(2) as an event in which equipment is disabled or fails  |
| to function as designed."  Paducah personnel notified the NRC resident       |
| inspector of this update.  The NRC operations officer notified the R3DO      |
| (Madera).                                                                    |
|                                                                              |
| * * * UPDATE 1440 EDT 6/18/1999 FROM UNDERWOOD TAKEN BY STRANSKY * * *       |
|                                                                              |
| "Two sprinkler heads on system C-15 and one sprinkler head on system B-8 in  |
| C-333 were identified to have corrosion.  The PSS was notified of this       |
| condition at 1350 CDT on 06/18/99.  The area of the fire patrol for system   |
| C-15 was expanded to include the two heads identified as corroded.  The one  |
| head on system B-8 was in the area already being patrolled.  The PSS         |
| determined that an update to this report was required."  The NRC resident    |
| inspector has been informed of this update.  Notified R3DO (Madera).         |
|                                                                              |
| * * * UPDATE 1315 EDT 6/25/1999 FROM WALKER TAKEN BY STRANSKY * * *          |
|                                                                              |
| "Two sprinkler heads on system D-8 and three sprinkler heads on system D-7   |
| in C-337 were identified to have corrosion.  The PSS was notified of the     |
| condition on system D-8 at 0125 CDT on 06/25/99 and at 1019 CDT on 06/25/99  |
| for system D-7.  Both systems were immediately declared inoperable and LCO   |
| fire patrol actions were implemented.  It was determined that an update to   |
| this report was required."  The NRC resident inspector has been informed of  |
| this update.  Notified R3DO (Jordan).                                        |
|                                                                              |
| * * * UPDATE 2119 EDT 7/30/1999 FROM CAGE TAKEN BY STRANSKY * * *            |
|                                                                              |
| "Five sprinkler heads and one sprinkler piping tee on C-337 system D-7 were  |
| identified to have corrosion. The PSS was notified of these corroded system  |
| parts and declared the system inoperable at 0931 CDT on 07/30/99.  LCO       |
| required fire patrols of the affected area were initiated.  The PSS          |
| determined that an update to this event report was required."  The NRC       |
| resident inspector has been informed of this update.  Notified R3DO          |
| (Wright).                                                                    |
|                                                                              |
| * * * UPDATE AT 1655 EDT ON 07/31/99 FROM WHITE TAKEN BY STRANSKY * * *      |
|                                                                              |
| "Two sprinkler heads on C-337 System D-1 were identified to have corrosion.  |
| The PSS was notified of these corroded system parts and declared the system  |
| inoperable at 1155 CDT on 7/31/99.  LCO required fire patrols of the         |
| affected area were initiated.  The PSS determined that an update to this     |
| report was required."  The NRC resident inspector has been informed of this  |
| update.  Notified R3DO (Wright).                                             |
|                                                                              |
| * * * UPDATE AT 1546 EDT ON 08/10/99 FROM WHITE TAKEN BY STRANSKY * * *      |
|                                                                              |
| "Two sprinkler heads on C-337 system C-15 were identified to have corrosion. |
| The PSS was notified of these corroded system parts and declared the system  |
| inoperable at 1130 CDT on 8/10/99.  LCO required fire patrols of the         |
| affected area were initiated.  The PSS determined that an update to this     |
| report was required."  The NRC resident inspector has been informed of this  |
| update.  Notified R3DO (Burgess).                                            |
|                                                                              |
| * * * UPDATE AT 1154 EDT ON 08/22/99 FROM WALKER TO POERTNER * * *           |
|                                                                              |
| Four adjacent sprinkler heads on the C-333 building System B-1 were          |
| identified to have corrosion.  The PSS was notified of the corroded system   |
| parts and declared the system inoperable at 0918 CDT on 08/22/99.  LCO       |
| required fire patrols were initiated.  The NRC Resident Inspector will be    |
| notified.  The NRC Operations Officer notified the R3DO (Clayton).           |
|                                                                              |
| * * * UPDATE 2015 EDT ON 08/28/99 FROM W. F. GAGE TO S. SANDIN * * *         |
|                                                                              |
| Two adjacent sprinkler heads on the C-337 building System D-11 were          |
| identified to have corrosion.  The PSS was notified of these corroded system |
| parts and declared the system inoperable at 1420 CDT on 08/28/99.   LCO      |
| required fire patrols of the affected area were initiated.  Paducah          |
| personnel informed the NRC Resident Inspector.  The NRC Operations Officer   |
| notified the R3DO (Leach) and NMSS EO (Piccone).                             |
|                                                                              |
| * * * UPDATE 2037 EDT ON 08/29/99 FROM KEVIN BEASLEY TO S. SANDIN * * *      |
|                                                                              |
| Two adjacent sprinkler heads on the C-337 building System D-15 were          |
| identified to have corrosion and the PSS declared the system inoperable at   |
| 0925 CDT on 08/29/99.  Also two adjacent heads on the C-337 building System  |
| D-10 were identified to have corrosion and the PSS declared the system       |
| inoperable at 1450 CDT.   LCO required fire patrols for both of the affected |
| areas were initiated in the time frame required by TSR.  Paducah personnel   |
| informed the NRC Resident Inspector.  The NRC Operations Officer notified    |
| the R3DO (Leach) and NMSS EO (Piccone).                                      |
|                                                                              |
| * * * UPDATE AT 0930 EDT ON 09/01/99  BY ERIC WALKER TO FANGIE JONES * * *   |
|                                                                              |
| Add two adjacent sprinkler heads on the C-337 building System D-14 were      |
| declared inoperable.  Paducah personnel informed the NRC Resident Inspector. |
| The NRC Operations Officer notified the R3DO (David Hills) and NMSS (Robert  |
| Pierson).                                                                    |
|                                                                              |
| * * * UPDATE AT 1133 EDT ON 09/08/99  BY TOM WHITE TO FANGIE JONES * * *     |
|                                                                              |
| Add two adjacent sprinkler heads on the C-331 building System 26 were        |
| declared inoperable at 2155 CDT on 09/07/99.  An LCO required fire patrol    |
| for the affected area was initiated in the time frame required by the TSR.   |
| Paducah personnel informed the NRC Resident Inspector.  The NRC Operations   |
| Officer notified the R3DO (Monte Phillips) and NMSS (Josie Piccone).         |
|                                                                              |
| * * * UPDATE AT 0948 ON 09/30/99 BY ERIC WALKER TO DOUG WEAVER * * *         |
|                                                                              |
| Add two adjacent sprinkler heads on the C-333 building System B-15 were      |
| identified to have corrosion and the PSS declared the system inoperable at   |
| 0815 CDT on 9/30/99.  An LCO required fire patrol for the affected area was  |
| initiated in the time frame required by the TSR.  Paducah personnel informed |
| the NRC Resident Inspector.   The NRC operations officer notified the R3DO   |
| (Vegel) and NMSS (Cool).                                                     |
|                                                                              |
| * * * UPDATE AT 1600 ON 10/13/99 BY WALKER TO GOULD * * *                    |
|                                                                              |
| Two adjacent sprinkler heads on the C-333 building System A-11 were          |
| Identified to have corrosion and the PSS declared the system inoperable at   |
| 1307 CDT on 10/13/99.  An LCO required fire patrol for the affected area was |
| initiated in the time frame required by the TSR.  Paducah personnel informed |
| the NRC Resident Inspector.   The NRC operations officer notified the R3DO   |
| (Madera) and NMSS (Moore).                                                   |
|                                                                              |
| * * * UPDATE AT 1520 ON 10/19/99 FROM UNDERWOOD TAKEN BY STRANSKY * * *      |
|                                                                              |
| Six sprinkler heads on the C-337 building System D-16 were identified to     |
| have corrosion and the PSS declared the system inoperable at 1052 CDT on     |
| 10/19/99.  An LCO required fire patrol for the affected area was initiated   |
| in the time frame required by the TSR.  The NRC Resident Inspector has been  |
| informed of this update.  The NRC Operations Officer notified R3DO           |
| (Jorgensen).                                                                 |
|                                                                              |
| * * * UPDATE AT 2140 ON 10/19/99 FROM WALKER TAKEN BY STRANSKY * * *         |
|                                                                              |
| Seven sprinkler heads on the C-337 building System A-7 were identified to    |
| have corrosion, and another four had been painted over.  In addition, three  |
| adjacent sprinkler heads on the C-337 building System A-8 were identified to |
| have corrosion.  The PSS declared the systems inoperable at 1900 CDT on      |
| 10/19/99.  An LCO required fire patrols for the affected areas were          |
| initiated in the time frame required by the TSR.  The NRC Resident Inspector |
| has been informed of this update.  The NRC Operations Officer notified R3DO  |
| (Wright).                                                                    |
|                                                                              |
| * * * UPDATE AT 1713 ON 10/21/99 FROM CAGE TAKEN BY JOLLIFFE * * *           |
|                                                                              |
| Four sprinkler heads on the C-337 building System A-5, twelve sprinkler      |
| heads on the C-337 building System A-8, three sprinkler heads on the C-337   |
| building System A-9, and six sprinkler heads on the C-337 building System    |
| B-8 were identified to have corrosion.  On 10/21/99, the PSS declared        |
| Systems A-5 and A-9 inoperable at 1028 CDT, System A-8 inoperable at 1227    |
| CDT and System B-8 inoperable at 1406 CDT.   An LCO required fire patrol for |
| the affected areas was initiated in the time frame required by the TSR..     |
| The NRC Resident Inspector has been informed of this update.  The NRC        |
| Operations Officer notified the R3DO Bruce Jorgensen.                        |
|                                                                              |
| * * * UPDATE AT 2128 ON 10/22/99 FROM ERIC WALKER TAKEN BY JOLLIFFE * * *    |
|                                                                              |
| At 1400 CDT on 10/22/99, the PSS was notified that numerous corroded         |
| sprinkler heads were discovered in the C-337 building on sprinkler systems   |
| B-1, B-3, B-5, B-6, B-7, B-11 and D-17.  Due to the number of systems called |
| into question, the PSS declared all of the sprinkler systems in C-337 on the |
| cell floor (a total of 66 systems) inoperable and TSR required actions       |
| establishing roving fire patrols were initiated within the required time     |
| frame.  The NRC Resident Inspector has been informed of this update.  The    |
| NRC Operations Officer notified the R3DO Bruce Jorgensen.                    |
|                                                                              |
| * * * UPDATE AT 1239 ON 10/24/99 FROM TOM WHITE TAKEN BY JOLLIFFE * * *      |
|                                                                              |
| At 1200 CDT on 10/23/99, the PSS was notified that numerous corroded         |
| sprinkler heads were discovered in the C-337 building on sprinkler systems   |
| B-13 and B-14 on the ground floor,  The PSS declared these systems           |
| inoperable and TSR required actions establishing roving fire patrols were    |
| initiated within the required time frame.  At 1600 CDT on 10/23/99, the PSS  |
| was notified that numerous corroded sprinkler heads were discovered in the   |
| C-337 building on sprinkler systems A-16, B-12, C-8, C-12, C-15, D-5 and D-8 |
| on the cell floor,  These systems have already been declared inoperable and  |
| fire patrols are already being performed.  The NRC Resident Inspector has    |
| been notified of this update.  The NRC Operations Officer notified the R3DO  |
| Bruce Jorgensen.                                                             |
|                                                                              |
| * * * UPDATE AT 1117 ON 10/25/99 FROM W. F. CAGE TAKEN BY SANDIN * * *       |
|                                                                              |
| At 1940 CDT on 10/24/99, the PSS was notified that numerous corroded         |
| sprinkler heads had been discovered on High Pressure Fire Water Systems C-4, |
| C-5, C-6 and C-8, located in the C-337 building.  These systems had          |
| previously been declared inoperable and fire patrols were already being      |
| performed at the time of discovery.  The NRC Resident Inspector has been     |
| notified of this update.  The NRC Operations Officer notified R3DO           |
| (Lanksbury) and NMSS (Brain Smith).                                          |
|                                                                              |
| * * * UPDATE AT 2235 ON 10/27/99 BY WHITE TAKEN BY MACKINNON * * *           |
|                                                                              |
| At 1517 CDT on 10/27/99, the PSS was notified that nine corroded sprinkler   |
| heads had been discovered on High Pressure Fire Water System A-12 located in |
| the C-333 building.  This system has been declared inoperable and fire       |
| patrols have been initiated.  The NRC Resident Inspector has been notified   |
| of this update.  The NRC Operations Officer notified R3DO (Jordan) and NMSS  |
| EO (Hickey).                                                                 |
|                                                                              |
| * * * UPDATE AT 2150 ON 10/30/99 BY UNDERWOOD TAKEN BY WEAVER * * *          |
|                                                                              |
| At 1950 CDT on 10/30/99, the PSS was notified that numerous corroded         |
| sprinkler heads had been discovered on High Pressure Fire Water Systems A-5, |
| A-9, A-11, C-5, and C-7 in the C-333 building.  Reference ATR-1 1999-6699    |
| and 6702.  These systems have been declared inoperable and fire patrols have |
| been initiated.  Also, due to the number of inoperable sprinkler heads, the  |
| remaining systems on the cell floor of C-333 were called into question and   |
| declared inoperable.  Fire patrols for the entire cell floor have been       |
| initialed.  The PSS determined that an update to this report was required.   |
| The NRC Resident Inspector has been notified of this update.  The NRC        |
| Operations Officer notified R3DO (Jordan) and NMSS EO (Hickey).              |
|                                                                              |
| * * * UPDATE AT 2111 ON 10/31/99 BY UNDERWOOD TAKEN BY WEAVER * * *          |
|                                                                              |
| At 1412 CDT on 10/31/99, the PSS was notified that five corroded sprinkler   |
| heads had been discovered on High Pressure Fire Water System 9 in the C-335  |
| building.  There were two adjacent corroded heads discovered in two separate |
| locations and a third individual head at a different location.  The system   |
| was declared inoperable and fire patrols were initiated.  The corroded heads |
| have since been replaced and the system returned to operable status.   The   |
| NRC Resident Inspector was notified of this update.  The NRC Operations      |
| Officer notified R3DO (Jordan) and NMSS EO (Hickey).                         |
|                                                                              |
| * * * UPDATE AT 2121 ON 11/01/99 BY KEVIN BEASLEY TAKEN BY JOLLIFFE * * *    |
|                                                                              |
| At 0930 CST on 11/01/99, the PSS was notified that three corroded sprinkler  |
| heads had been discovered on the High Pressure Fire Water System B-4 in the  |
| C-337 building.  Two of these sprinkler heads are adjacent.  Two adjacent    |
| corroded sprinkler heads were also discovered on the High Pressure Fire      |
| Water System B-5 in the C-337 building.  These systems were declared         |
| inoperable and fire patrols were initiated.  Work has been initiated to      |
| replace the corroded heads.  The NRC Resident Inspector has been notified of |
| this update.  The NRC Operations Officer notified the R3DO Jim Creed.        |
|                                                                              |
| * * * UPDATE AT 2143 ON 11/02/99 BY KEVIN BEASLEY TAKEN BY JOLLIFFE * * *    |
|                                                                              |
| At 1400 CST on 11/02/99, the PSS was notified that numerous corroded         |
| sprinkler heads had been discovered on High Pressure Fire Water Systems C-8  |
| and D-7 in the C-333 building.  These systems had been previously declared   |
| inoperable and fire patrols were being performed at the time of discovery.   |
| Work has been initiated to replace the corroded heads.  The NRC Resident     |
| Inspector has been notified of this update.  The NRC Operations Officer      |
| notified the R3DO Jim Creed.                                                 |
|                                                                              |
| * * * UPDATE AT 2110EST ON 11/4/99 FROM ERIC WALKER TO S. SANDIN * * *       |
|                                                                              |
| "At 1700 on 11/4/99, the Plant Shift Superintendent (PSS) was notified that  |
| numerous corroded sprinkler heads had been discovered on High Pressure Fire  |
| Water systems A-16, C-17, D-12, and D-16 in the C-333 building. These        |
| systems had been previously declared inoperable, and fire patrols were being |
| performed at the time of discovery. Work his been initiated to replace the   |
| corroded heads. The PSS determined that an update to this report was         |
| required.                                                                    |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| The NRC Senior Resident Inspector has been notified of this event.  Notified |
| R3DO(Creed) and NMSS EO(Hodges).                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36263       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SWAGELOK COMPANY                     |NOTIFICATION DATE: 10/06/1999|
|LICENSEE:  SWAGELOK COMPANY                     |NOTIFICATION TIME: 09:48[EDT]|
|    CITY:  Solon                    REGION:  3  |EVENT DATE:        10/04/1999|
|  COUNTY:                            STATE:  OH |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  11/04/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN KINNEMAN        R1      |
|                                                |BRIAN BONSER         R2      |
+------------------------------------------------+JOHN JACOBSON        R3      |
| NRC NOTIFIED BY:  BRUCE FLUSCHE (Fax)          |KRISS KENNEDY        R4      |
|  HQ OPS OFFICER:  LEIGH TROCINE                |VERN HODGE           NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSSIBLE 10-CFR-PART-21 REPORT REGARDING A POSSIBLE DEFECT IN A SWAGELOK     |
| TUBE FITTING                                                                 |
|                                                                              |
| The following text is a portion of a facsimile submitted by Swagelok         |
| Company:                                                                     |
|                                                                              |
| "This is a preliminary notification of a possible defect in a Swagelok tube  |
| fitting, part number SS-400-3-4TTM, male branch tee.  A drawing of the part  |
| is included with this notification.  We are also notifying each of the       |
| involved utilities."                                                         |
|                                                                              |
| "We became aware of this on October 4, 1999."                                |
|                                                                              |
| "The defect is a crack in the seat of the fitting.  We are continuing our    |
| analysis of the part and will provide further details in accordance with NRC |
| timetables."                                                                 |
|                                                                              |
| "[The] following are the six utilities to whom we have sold these parts:     |
|                                                                              |
| Georgia Power [Company], Plant Vogtle, ... , 10 pcs. ... [;]                 |
| Duke Power Company, Oconee Nuclear Station, ... ,100 pcs. ... [;]            |
| Arizona Public Service Co., Palo Verde Nuclear Generating Station, ... , 15  |
| pcs. ... [;]                                                                 |
| North Atlantic Energy Service Co., ... , Seabrook Station, ... ,10 pcs. ...  |
| [;]                                                                          |
| Virginia Power, Surry Power Station, ... , 3 pcs. ... [; and]                |
| Omaha Public Power District, Ft. Calhoun Nuclear Station, ... , 10 Pcs. ...  |
| ."                                                                           |
|                                                                              |
| (Call the NRC operations officer for Swagelok contact information.)          |
|                                                                              |
| * * * UPDATE 1553 EST ON 11/4/99 FROM BRUCE FLUSCHE TO S. SANDIN * * *       |
|                                                                              |
| The following information was received via fax:                              |
|                                                                              |
| "We are writing further to our preliminary notification on October 6,1999    |
| about a possible defect in a Swagelok tube fitting, part number              |
| SS-400-3-4TTM, male branch tee.                                              |
|                                                                              |
| "The utilities to whom we have sold this are repeated in the appendix to     |
| this letter.                                                                 |
|                                                                              |
| "As we reported earlier, the defect is a crack in the seat of the fitting.   |
| This crank resulted from overheating during the resistive type heated        |
| forging process; it was not a defect in the raw material. The estimated per  |
| cent of forgings that have this condition is less than 0.03%.                |
|                                                                              |
| "This forging was processed in December of 1996.  Since the middle of 1998   |
| we have required liquid penetrant testing on all resistive type heated       |
| forgings.                                                                    |
|                                                                              |
| "If there are any questions, please do not hesitate to contact us."          |
|                                                                              |
| Notified the R1DO (Mohamed Shanbaky), R2DO (Pierce Skinner), R3DO (James     |
| Creed), and R4DO (Claude Johnson).  Faxed to NRR part 21 (Vern Hodges).      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36394       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 11/04/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 07:56[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        11/03/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:45[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/04/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JAMES CREED          R3      |
|  DOCKET:  0707002                              |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  McCLEERY                     |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LEGACY ITEM  -  TWO ERRORS OCCURRED ON A U235 MASS LOG                       |
|                                                                              |
| NRC BULLETIN 91-01 24 HOUR NOTIFICATION                                      |
|                                                                              |
| On 1/3/99 at 1645 hrs the Plant Shift Superintendent (PSS) was notified that |
| a Nuclear Criticality Safety Approval                                        |
| (NCSA) requirement was not being performed in the X-710 ES&H Analytical      |
| Labs. Building personnel identified that two errors had occurred on the U235 |
| mass log which is used for NCSA compliance verification. The first error was |
| a [non-conservative] mathematical addition error causing an incorrect total  |
| to be reported on the Mass log. The second error was that a sample container |
| was inadvertently not logged in on the mass log. This NCS anomaly is a       |
| legacy item in that this error was entered into the log on March of 1998.    |
|                                                                              |
| Requirement 1 of NCSA-0710_25.AOO states in part; Samples in any room        |
| enriched to 1% or greater U235, will be limited to one group of (30g U235)   |
| per room. This will be ensured by maintaining a room inventory log of U235   |
| mass in labeled containers. Each log entry will consist of the U235 mass     |
| value plus analytical uncertainty and will be:                               |
|                                                                              |
| a. made by a knowledgeable person "PRIOR" to bring the samples into the      |
| room, and                                                                    |
| b. verified by a second knowledgeable person "PRIOR" to bringing the samples |
| into the room.                                                               |
|                                                                              |
| Both errors were in the non-conservative direction, but the total mass limit |
| for the room 30g U235 was never exceeded [actual amount was 28.851g]. These  |
| errors show that both the first and second contingency control were          |
| violated.                                                                    |
|                                                                              |
| At the direction of the Plant Shift Superintendent the requirements for an   |
| NCS anomalous condition were initiated and the area boundaried off           |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL. CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.  |
|                                                                              |
| SAFETY SIGNIFICANCE OF THE EVENT:                                            |
|                                                                              |
| The safety significance of the event is low.  The U235 mass in the group was |
| never above the NCSA requirement.  However, both controls on the mass        |
| requirement were violated.                                                   |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAY INVOLVED (BRIEF SCENARIOs OF HOW CRITICALITY   |
| COULD OCCUR):                                                                |
|                                                                              |
| Repeated mass violations could result in a greater than safe mass being in   |
| the room. Since moderation is not controlled, a spacing violation could have |
| allowed the uranium to reach a critical configuration.                       |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.);     |
|                                                                              |
| Mass, volume, and interaction (spacing) was controlled.  By incorrectly      |
| logging the mass of one sample and neglecting to log the mass of a separate  |
| sample,  both the first and second contingency controls was violated.        |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDED PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| The highest mass of U235 in the group was 28.851 grams.  Enrichment of this  |
| operation is not controlled, but it is not expected to be 10% assay due to   |
| plant production limitations.  The form of the uranium varies based on the   |
| specific samples involve, although uranyl fluoride, uranyl nitrate, uranium  |
| tetra fluoride and other forms would be expected.  This represents less than |
| 4% of critical mass.                                                         |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(s) OR CONTROL SYSTEM(s)  AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES                                              |
|                                                                              |
| The control on this process included a first and second check to ensures the |
| U235 mass of each sample is recorded and a running total maintained to       |
| prevent exceeding a limit of 30 grams U235.  Both the first and second check |
| were violated in two separate cases.                                         |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:   |
|                                                                              |
| At the direction of the Plant Shift Superintendent the requirements for an   |
| NCS anomalous condition were initiated and the are boundaried off.  Lab      |
| personnel made corrections to log error and mass was verified at 1700        |
| hours.                                                                       |
|                                                                              |
| The NRC Resident Inspector was notified of this legacy event by the          |
| certificate holder.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36395       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 11/04/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 14:09[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/04/1999|
+------------------------------------------------+EVENT TIME:        11:36[CST]|
| NRC NOTIFIED BY:  TODD STRAIN                  |LAST UPDATE DATE:  11/04/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT SAFEGUARDS ACTUATIONS DURING PLANNED ELECTRICAL MAINTENANCE      |
|                                                                              |
| "AT 1136CST ON 11/4/99, SAFEGUARDS 4.16KV BUS '16' DE-ENERGIZED UNEXPECTEDLY |
| WHEN THE OFFSITE SOURCE SUPPLYING THE BUS TRIPPED.  THE BUS WAS              |
| AUTOMATICALLY REPOWERED WITH THE AUTOMATIC CLOSURE OF ANOTHER OFFSITE SOURCE |
| BREAKER.  [THE] CAUSE OF THE DE-ENERGIZATION WAS AN INADVERTENT 'CT11'       |
| (NORMAL OFFSITE SUPPLY TO SAFEGUARDS BUS '16') LOCKOUT, DUE TO A BUMPED      |
| RELAY WHILE RE-INSTALLING A 4KV BREAKER INTO ITS CUBICLE.                    |
|                                                                              |
| "AUTO ACTUATIONS AS A RESULT OF THE MOMENTARY DE-ENERGIZATION WERE:          |
|                                                                              |
| 1.  AUTOSTART OF THE OPPOSITE TRAIN COMPONENT COOLING WATER PUMP, AND        |
| 2.  AUTO SEQUENCING OF BUS '16' TO AN ALTERNATE SOURCE."                     |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36396       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  PRINCETON MEDICAL CENTER             |NOTIFICATION DATE: 11/04/1999|
|LICENSEE:  PRINCETON MEDICAL CENTER             |NOTIFICATION TIME: 14:30[EST]|
|    CITY:  PRINCETON                REGION:  1  |EVENT DATE:        11/04/1999|
|  COUNTY:                            STATE:  NJ |EVENT TIME:        09:15[EST]|
|LICENSE#:  29-06750-01           AGREEMENT:  N  |LAST UPDATE DATE:  11/04/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  EDWARD BACZA                 |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL MISADMINISTRATION INVOLVING DISLODGED BRACHYTHERAPY SOURCE         |
|                                                                              |
| AT APPROXIMATELY 0915EST AN ELDERLY FEMALE PATIENT NOTIFIED HOSPITAL STAFF   |
| THAT A BRACYTHERAPY SOURCE (Cs-137 - 21.8 MILLIGRAM RADIUM EQUIVALENT) HAD   |
| BECOME DISLODGED.  HOSPITAL STAFF CONTACTED THE PHYSICIAN THAT HAD INSERTED  |
| THE SOURCE AND WAS INSTRUCTED TO RELOCATE THE APPLICATOR TO THE FOOT OF THE  |
| BED.  THE HOSPITAL PHYSICIST ESTIMATES THAT THE SOURCE WAS IN THE VICINITY   |
| OF THE PATIENT'S THIGH FOR APPROXIMATELY 15 MINUTES AND AT THE FOOT THE BED  |
| FOR ANOTHER 18 MINUTES BEFORE BEING PLACED IN A LEAD PIG.  THE ATTENDING     |
| PHYSICIAN DOES NOT INTEND ANY ADDITIONAL EXPOSURE SINCE THE SOURCE REMAINED  |
| IN PLACE FOR 18.45 OF THE 22.79 HOURS PRESCRIBED.  NO ADVERSE HEALTH         |
| CONSEQUENCES ARE EXPECTED.                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36397       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 11/04/1999|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 15:06[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        11/04/1999|
+------------------------------------------------+EVENT TIME:        10:00[EST]|
| NRC NOTIFIED BY:  BRIAN STETSON                |LAST UPDATE DATE:  11/04/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| CONTROL ROD WITHDRAWAL LIMITER DISCOVERED INOPERABLE DURING ROD TESTING      |
|                                                                              |
| "It has been discovered that following the insertion of a control rod, the   |
| Rod Withdrawal Limiter is inoperable until that control rod is deselected    |
| and reselected from the Rod Control & Information System control panel.      |
|                                                                              |
| "We have reasonable knowledge that we have withdrawn control rods in the     |
| past, while the Rod Withdrawal Limiter has been inoperable. We have specific |
| knowledge that on 10/31/99, a control rod was withdrawn with the Rod         |
| Withdrawal Limiter inoperable. This is a violation of Technical              |
| Specification 3.3.2.1 Action A.1.                                            |
|                                                                              |
| "This report is required due to the requirements of the Operating License    |
| for a violation of Technical Specifications."                                |
|                                                                              |
| This condition was discovered by operators during performance of control rod |
| speed adjustment of a single rod.  Control rod motion continued past the     |
| withdrawal notch limit of 4.  The operator immediately let go of the         |
| withdraw push button causing the rod to stop at the notch 6 position.  The   |
| licensee suspects this condition has existed since initial construction and  |
| has imposed administrative controls specifically referencing Technical       |
| Specifications requirements.                                                 |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36398       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 11/04/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:04[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        11/04/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        08:25[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/04/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JAMES CREED          R3      |
|  DOCKET:  0707002                              |WAYNE HODGES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILURE DURING AUTOCLAVE HEATUP                             |
|                                                                              |
| "ON 11/4/99 AT 0825 [HOURS] OPERATORS IN THE X-344 NOTICED CONDENSATE        |
| LEAKING FROM THE AUTOCLAVE #2 LOCKING RING AREA WHILE IN MODE II (HEATING).  |
| THE AUTOCLAVE WAS PLACED IN MODE VII (SHUTDOWN) 15 MINUTES AFTER THE         |
| DISCOVERY OF THE LEAK. INITIAL INVESTIGATION SHOWS A PIECE OF COPPER TUBING  |
| MAY HAVE BEEN LODGED ON THE SEALING SURFACE OF THE LOCKING RING. THE         |
| AUTOCLAVE WAS MADE INOPERABLE IMMEDIATELY. THERE WAS NO ACTUATION OF A       |
| SAFETY SYSTEM DURING THIS OPERATION. THIS IS REPORTABLE UNDER CONDITION      |
| 76.120 (C)(2)(i), AN EVENT IN WHICH EQUIPMENT IS DISABLED OR FAILS TO        |
| FUNCTION AS DESIGNED WHEN THE EQUIPMENT IS REQUIRED BY A TSR [TECHNICAL      |
| SAFETY REQUIREMENT] TO PREVENT RELEASES.                                     |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."  |
|                                                                              |
| OPERATION'S STAFF NOTIFIED THE NRC RESIDENT INSPECTOR AND DOE SITE           |
| REPRESENTATIVE.                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36399       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/04/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 18:29[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/04/1999|
+------------------------------------------------+EVENT TIME:        14:00[CST]|
| NRC NOTIFIED BY:  JOHN SELL                    |LAST UPDATE DATE:  11/04/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|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        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TWO MAIN STEAM SAFETY VALVES (MSSVs) EXCEEDED ACCEPTANCE CRITERIA DURING     |
| SETPOINT TESTING                                                             |
|                                                                              |
| "DURING THE POINT BEACH NUCLEAR PLANT (PBNP) UNIT 1 R25 OUTAGE, TWO (2) MAIN |
| STEAM SAFETY VALVES WERE SENT TO WYLE LABS FOR SETPOINT TESTING.  MS-02013   |
| LIFTED AT 2.4% ABOVE NAMEPLATE SETPOINT OF 1125 PSIG.  THE OWNER ACCEPTANCE  |
| CRITERIA IS 1.93%.  THIS VALVE DID NOT EXCEED THE ASME ACCEPTANCE CRITERIA   |
| OF 3%.                                                                       |
|                                                                              |
| "MS-02012 LIFTED AT 3.7% ABOVE THE NAMEPLATE SETPOINT OF 1125 PSIG.  THIS    |
| EXCEEDS BOTH THE OWNER ESTABLISHED ACCEPTANCE CRITERIA AND THE ASME XI       |
| CRITERIA.                                                                    |
|                                                                              |
| "PBNP TECH SPECS REQUIRE AN ADDITIONAL NUMBER OF VALVES TO BE TESTED EQUAL   |
| TO THE NUMBER ORIGINALLY TESTED.  SINCE FOUR (4) MSSVs WERE SENT FOR TESTING |
| THIS OUTAGE, THE REMAINING FOUR (4) MSSVs WILL NEED TO BE TESTED.            |
|                                                                              |
| "BOTH MS-02012 AND MS-02013 MAY HAVE HAD THEIR SETPOINTS ADJUSTED            |
| INCORRECTLY IN 1995."                                                        |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36400       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 04:07[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/04/1999|
+------------------------------------------------+EVENT TIME:        20:30[CST]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|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        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 0.25 INCH LONG CRACK WAS FOUND ON "1A" STEAM GENERATOR HEAD DRAIN VALVE.     |
|                                                                              |
| During a liquid penetrant examination of a weld on the top side of valve     |
| 1R-526A, "1A" Steam Generator head drain, a 0.25" long crack was found.      |
| Appears o be a crack in the weld metal only, through wall of the Reactor     |
| Coolant System pressure boundary.                                            |
|                                                                              |
| During initial screening of this condition at 2030 hours on 11/04/99 it was  |
| not considered seriously degraded as no leak was detected while at power     |
| (boric acid crystals were found in the vicinity of the valve).  Upon further |
| review at 0200 hours on 11/05/99 this 4 hour non-emergency report was made.  |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36401       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 05:21[EST]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        11/05/1999|
+------------------------------------------------+EVENT TIME:        02:32[CST]|
| NRC NOTIFIED BY:  TIM SMITH                    |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STEAM GENERATOR BLOWDOWN ISOLATION VALVE CLOSED                              |
|                                                                              |
| At 0232 on 11/05/99 Radiation Monitor R-19 Steam Generator liquid failed.    |
| This failure caused the Steam Generator blowdown isolation valves;           |
| BT-2A/MV-32077 Steam Generator blowdown isolation valve A1, BT-2B/MV-32079   |
| Steam Generator blowdown isolation valve B1, BT-3A/MV-32078 Steam Generator  |
| blowdown isolation valve A2, and BT-3B/MV-32080 Steam Generator blowdown     |
| isolation valve B2, to close.  These valves have a containment isolation     |
| function for a Main Steam Line Rupture within containment.  Their Post -     |
| Loss of Coolant Accident function is to provide Steam Generator isolation.   |
|                                                                              |
|                                                                              |
| The monitor failure will not allow the re-establishment of Steam Generator   |
| blowdown flow.  Plant Chemistry and Instrument and Control personnel have    |
| been contacted to determine corrective actions and to repair the radiation   |
| monitor.  Radiation Monitor R-15, Air Ejector Exhaust, is indicating normal  |
| readings and is being monitored by operations.  Local indication of          |
| Radiation Monitor R-19 are the normal count rate. Actual problem appears to  |
| be the Control Room indication of R-19 failed.                               |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+