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Event Notification Report for May 7, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/06/1999 - 05/07/1999

                              ** EVENT NUMBERS **

35591  35650  35679  35682  35683  35684  35685  35686  35687  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35591       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 04/14/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 04:32[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        04/14/1999|
+------------------------------------------------+EVENT TIME:        01:28[CDT]|
| NRC NOTIFIED BY:  FRED SCHIZAS                 |LAST UPDATE DATE:  05/06/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - RCIC SYSTEM DECLARED INOPERABLE DUE TO FAILED SYSTEM COOLING VALVE DURING  |
| A TEST -                                                                     |
|                                                                              |
| AT 0128 CDT ON 04/14/99, THE LICENSEE DECLARED THE REACTOR CORE ISOLATION    |
| COOLING (RCIC) SYSTEM INOPERABLE DUE TO THE FAILURE OF THE RCIC SYSTEM       |
| COOLING VALVE, #RCIC-MO-132.  WHEN THE VALVE CONTROL SWITCH WAS PLACED IN    |
| THE CLOSE POSITION IN ORDER TO RECORD THE VALVE STROKE TIME DURING THE RCIC  |
| POWER-OPERATED VALVE OPERABILITY SURVEILLANCE TEST, THE VALVE MOVED TO THE   |
| INTERMEDIATE POSITION AND STOPPED.  STATION OPERATORS VERIFIED THAT THE      |
| VALVE WAS NOT CLOSED AND ISOLATED THE RCIC SYSTEM STEAM SUPPLY AND SUCTION   |
| AND DISCHARGE PATHS IN ORDER TO PREVENT SYSTEM INITIATION, EVIDENCE          |
| PRESERVATION, AND EXCESSIVE CYCLING OF THE BAROMETRIC CONDENSER PUMP.        |
| STATION OPERATORS ALSO VERIFIED THAT THE HIGH PRESSURE COOLANT INJECTION     |
| SYSTEM WAS OPERABLE.                                                         |
|                                                                              |
| TECH SPEC LCO A/S 3.5.3.A REQUIRES THE LICENSE TO RESTORE THE RCIC SYSTEM TO |
| OPERABLE STATUS WITHIN 14 DAYS OR SHUT THE PLANT DOWN.                       |
|                                                                              |
| STATION OPERATORS ARE INVESTIGATING THE CAUSE OF THE VALVE FAILURE AND PLAN  |
| TO REPAIR THE VALVE.                                                         |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| *** UPDATE ON 5/6/99 @ 1444 FROM SCHIZAS TO GOULD ***  RETRACTION            |
|                                                                              |
| OPERATION OF THE RCIC SYSTEM REQUIRES THE "RCIC-MOV-MO132" VALVE TO REMAIN   |
| OPEN.  IT WAS DISCOVERED THAT THE FAILURE OF THIS VALVE WAS FOUND TO BE IN   |
| THE CLOSING STROKE POSITION ONLY.  THIS VALVE WAS STROKED OPEN SUCCESSFULLY  |
| PRIOR TO AND DURING TROUBLESHOOTING.  SINCE THE VALVE WAS ALMOST OPEN WHEN   |
| IT FAILED, IT IS CONCLUDED THAT THE RCIC SYSTEM COULD HAVE PERFORMED ITS     |
| SAFETY FUNCTION AND WAS NOT AFFECTED BY THE MALFUNCTION OF THE               |
| "RCIC-MOV-MO132" VALVE DURING THE CLOSING STROKE. THEREFORE, THIS EVENT IS   |
| NOT REPORTABLE AND IS BEING RETRACTED.                                       |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| REG 4 RDO(JONES) WAS NOTIFIED.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35650       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 04/29/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 08:28[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/28/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:15[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/06/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |JOHN MADERA          R3      |
|  DOCKET:  0707001                              |FREDERICK COMBS      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT                                            |
|                                                                              |
| The following is text from a facsimile submitted to the NRC Operations       |
| Center:                                                                      |
|                                                                              |
| "During a walkdown of C-710, room 6, a group of small chemical traps with    |
| tags indicating less than 5 pounds of uranium were discovered in violation   |
| of [the] NCSA GEN-10 two-foot spacing requirement for UH pieces of           |
| equipment. These items were improperly categorized as spacing exempt based   |
| on the size criteria of having dimensions in all directions greater than     |
| that of a 5.5 gallon drum. Fifty-three items would be required prior to      |
| exceeding the UH mass at 2.0 wt. % U235. Similar incidents involving the     |
| violation were also discovered in C-710, room 2, C-409, and C-720. GEN-10    |
| states that UH items must be spaced a minimum of two feet edge-to-edge from  |
| other UH items to preclude the accumulation of an unsafe uranium mass.       |
|                                                                              |
| "This event is being categorized as a 24-hour event in accordance with       |
| Safety Analysis Report Table 6.9-1, Criterion A4.a, and Bulletin 91-01,      |
| Supplement 1.                                                                |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
|                                                                              |
| "Although the amount of Fissile material present is far below safe mass for  |
| each item, double contingency was not maintained because the items were not  |
| handled as UH and properly spaced.                                           |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW           |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| "In order for a criticality to be possible, greater than 104 of these items  |
| which contain less than 5 pounds of uranium each would need to be            |
| accumulated.                                                                 |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
|                                                                              |
| "Interaction and mass                                                        |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE CRITICAL MASS):                                       |
|                                                                              |
| "Variable amount. 2.0 wt. % U235, in the form of UO2F2, with a process limit |
| of approximately 600 lbs. at 2.0 wt. % U235                                  |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| "The two process conditions relied on in this scenario for double            |
| contingency are mass and interaction.                                        |
|                                                                              |
| "The first leg of double contingency is based on limiting the mass of        |
| uranium at 2.0 wt. % U235 to 264 pounds of uranium. This is controlled by    |
| quantifying the mass of each item using independent NDAs/visual inspections. |
| Each individual item contains less than 5 pounds of uranium: therefore, this |
| control was not violated. The total mass of all the items placed together at |
| each location is less than the UH mass limit.                                |
|                                                                              |
| "The second leg of double contingency is based on limiting interaction       |
| between UH items. This is controlled by maintaining minimum two-foot         |
| edge-to-edge spacing between UH items. Spacing was not maintained between    |
| the items: therefore, this requirement was violated and the process          |
| condition was lost,                                                          |
|                                                                              |
| "Since a control relied upon for double contingency was violated, double     |
| contingency was lost."                                                       |
|                                                                              |
| The NRC resident inspector has been informed of this notification.           |
|                                                                              |
| * * * * * * * * * * UPDATE AT 1212 EDT ON 05/05/99 FROM TOM WHITE TO FANGIE  |
| JONES * * * * * * * * * *                                                    |
|                                                                              |
| "Plant walkdowns have revealed additional locations which are also           |
| inappropriately spaced under GEN-10 criteria.  These additional locations    |
| are:                                                                         |
|                                                                              |
| C-335, 15 pallets of valve parts, totaling less than 52 items                |
| C-400, 2 centrifugal pump casings                                            |
|                                                                              |
| "The amount of fissile material is far below the safe mass for each item and |
| is less than the number of items needed to be greater than a safe mass.  NCS |
| incident report NCS-INC-99-024 has been revised to encompass these new       |
| locations."                                                                  |
|                                                                              |
| The NRC resident inspector has been notified of this update, and the onsite  |
| Department of Energy site representative will be notified by Paducah         |
| personnel.  The NRC Headquarters Operations Officer notified the R3DO (Monte |
| Phillips), NMSS EO (Don Cool), and IRO (Frank Congel)                        |
|                                                                              |
| **** UPDATE ON 5/6/99 @ 1711 FROM WHITE TO GOULD ****                        |
|                                                                              |
| DURING A PLANT WALKDOWN, AN ADDITIONAL LOCATION WAS REVEALED THAT IS ALSO    |
| INAPPROPRIATELY SPACED UNDER GEN-10 CRITERIA.  THE LOCATION IS C-720 STORES  |
| WHICH HAS FOUR 4" AND TWO 6" G-17 VALVES.  THE AMOUNT OF FISSILE MATERIAL IS |
| FAR BELOW THE SAFE MASS FOR EACH ITEM AND IS LESS THAN THE NUMBER OF ITEMS   |
| NEEDED TO BE GREATER THAN A SAFE MASS.  NCS INCIDENT REPORT NCS-INC-99-024   |
| HAS BEEN REVISED TO ENCOMPASS THE NEW LOCATION.                              |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
|                                                                              |
| THE REG 3 RDO(PHILLIPS) AND NMSS EO(GREEVES) WERE NOTIFIED                   |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35679       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 05/05/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 13:08[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/04/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        12:10[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/06/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707001                              |DON COOL             NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  TOM WHITE                    |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 24-HOUR REPORT, LOSS OF CRITICALITY CONTROL               |
|                                                                              |
| "On 05/04/99 at 1210 CDT, while performing a walkdown of C-333 for GEN-10    |
| items, a 'square-to-round process pipe' was discovered which did not have an |
| NCS tagging, posting, or NCSA controls applied.  It is believed that this    |
| equipment has been exposed to process gas.  If the square-to-round contains  |
| fissile material, it should have been controlled under GEN-010 or NCSA       |
| GEN-20/27.  The controls provided in these NCSAs ensure compliance with the  |
| double contingency principle.  An Nondestructive Analysis has been performed |
| on this equipment with results indicating mass of uranium being much less    |
| than the safe mass.  However, no NCS controls were applied, double           |
| contingency cannot be demonstrated for this equipment, and double            |
| contingency was lost.                                                        |
|                                                                              |
| "This event is being categorized as a 24-hour event in accordance with       |
| Safety Analysis Report Table 6.9-1, Criteria A.4.a, and Bulletin 91-01,      |
| Supplement 1 report.                                                         |
|                                                                              |
| "PGDP Problem Report No. ATR-99-2568, PGDP Event Report No. PAD-1999-034,    |
| Event Worksheet 35679.                                                       |
|                                                                              |
| "The NRC Senior resident inspector has been notified of this event."         |
|                                                                              |
| *** UPDATE ON 5/6/99 @ 1401 BY  WALKER TO GOULD *** EVENT RETRACTION         |
|                                                                              |
| AN ASSAY VERIFICATION HAS BEEN COMPLETED AND IT INDICATES THE MATERIAL ON    |
| THE PIPE TO BE NON-FISSILE(.711% wt U).  THUS, THE PIPE IS NCS EXEMPT, AND A |
| VIOLATION OF NCS CONTROLS DID NOT OCCUR MAKING A NOTIFICATION TO NRC NOT     |
| REQUIRED.  THEREFORE, THEY ARE RETRACTING THIS EVENT.                        |
|                                                                              |
| THE RESIDENT HAS BEEN NOTIFIED.                                              |
|                                                                              |
| THE REG 3 RDO(PHILLIPS)  AND NMSS EO(GREEVES) WERE NOTIFIED.                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35682       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 05/06/1999|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 07:34[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        05/06/1999|
+------------------------------------------------+EVENT TIME:        06:45[EDT]|
| NRC NOTIFIED BY:  JIM PROPER                   |LAST UPDATE DATE:  05/06/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ATTEMPTED INTRODUCTION OF CONTRABAND INTO THE PROTECTED AREA  (1-hour report |
| in accordance with 10 CFR 73.71, Appendix G)                                 |
|                                                                              |
| The licensee reported an attempted introduction of contraband into the       |
| protected area.  Immediate compensatory measurements were taken upon         |
| discovery.  (Contact the NRC operations officer for additional details and   |
| for a site contact telephone number.)                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35683       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 05/06/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 09:24[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/05/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:30[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/06/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707002                              |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JEFF CASTLE                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBC 76.120(c)(2)(iii)   REDUNDANT EQUIP INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF TWO INOPERABLE ADJACENT SMOKEHEADS (24-hour report - Safety     |
| Equipment Failure)                                                           |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth:     |
|                                                                              |
| "On 05/05/99 at 1430 hours, it was discovered that two adjacent smokeheads   |
| (S13 and S14) in [the] X-330 building 31-3-1 cell housing were not operable. |
| The second smokehead in 31-3-1 (S13) was not declared inoperable at the time |
| of failure resulting in a violation of TSR 2.2.3.3 and a failure to enter    |
| the [limiting condition for operation (LCO)] required by TSR 2.2.3.3, action |
| A.1.  The LCO was not entered as required on 05/02/99 at 1132 hours.  The    |
| second smokehead (S13) was declared inoperable on 05/03/99 at 0828 hours at  |
| which time a smoke watch was stationed, and TSR compliance was established.  |
| Smokehead S14 was repaired and declared operable on 05/03/99 at 1330 hours   |
| at which time the LCO was exited (50% coverage was restored)."               |
|                                                                              |
| "There was no loss of hazardous/radioactive material or                      |
| radioactive/radiological contamination exposure as a result of this event."  |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector and the Department  |
| of Energy site representative.                                               |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35684       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 05/06/1999|
|    UNIT:  [1] [2] [3]               STATE:  AL |NOTIFICATION TIME: 09:51[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        05/06/1999|
+------------------------------------------------+EVENT TIME:        08:35[CDT]|
| NRC NOTIFIED BY:  DON SMITH                    |LAST UPDATE DATE:  05/06/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    R2      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          N       0        Startup          |0        Startup          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS INOPERABLE DUE TO WEATHER                                   |
|                                                                              |
| The licensee reported that 35 of 100 emergency sirens are currently          |
| inoperable due to adverse weather conditions.  The plant is required to      |
| maintain at least 70 sirens operable at any time.  The licensee is           |
| attempting to restore the sirens, but stated that the adverse weather is     |
| expected to continue throughout the day.  The NRC resident inspector has     |
| been informed of this notification.                                          |
|                                                                              |
| ***UPDATE ON 5/6/99 @ 1552 BY SMITH TO GOULD ***  EVENT RETRACTION           |
|                                                                              |
| THE LICENSEE IS RETRACTING THIS EVENT SINCE IT WAS DETERMINED THAT ONLY 1    |
| SIREN WAS                                                                    |
| INOPERABLE OUT OF 35.  THE ABILITY TO VERIFY OPERABILITY OF THE OTHER 34     |
| SIRENS WAS MASKED BY THE 1 INOPERABLE SIREN.  THE INOPERABLE SIREN WAS       |
| RETURNED TO SERVICE AT 1300CST.                                              |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| REG 2 RDO(CHRISTENSEN) WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35685       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 05/06/1999|
|    UNIT:  [] [2] [3]                STATE:  CA |NOTIFICATION TIME: 15:12[EDT]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        05/05/1999|
+------------------------------------------------+EVENT TIME:             [PDT]|
| NRC NOTIFIED BY:  WILLIAMS                     |LAST UPDATE DATE:  05/06/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|10 CFR SECTION:                                 |VERN HOGE (FAX)      NRR     |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE HAS DETERMINED THAT A MANUFACTURING DEFECT IS PRESENT ON SOME   |
| OF THE POTTER AND BRUMFIELD (P&B) RELAYS THEY HAVE AT THE SITE.              |
|                                                                              |
| SIXTEEN P&B RELAYS, MODEL KUP93-14A32-120, WERE SUPPLIED IN LOT #913501 BY   |
| THE VENDOR AS COMMERCIAL GRADE ITEMS AND WERE DEDICATED FOR NUCLEAR SERVICE  |
| AT SAN ONOFRE.  THE LICENSEE'S LAB ANALYSIS OF FOUR OF THESE RELAYS          |
| DETERMINED THE CONTACT PADS WERE INSUFFICIENTLY WELDED TO THEIR CONTACT ARMS |
| AND COULD BECOME DETACHED.  BASED ON THEIR REVIEW OF RELAY FAILURE HISTORY,  |
| THE LICENSEE CONCLUDED THE INSUFFICIENT CONTACT PAD WELDING IS LIMITED TO    |
| LOT #913501.                                                                 |
|                                                                              |
| THESE RELAYS HAVE BEEN REPLACED WITH NEW P&B RELAYS WHICH HAVE THE CONTACT   |
| PADS RIVETED TO THEIR CONTACT ARM, THUS PRECLUDING ANY CONTACT DETACHMENT.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35686       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 05/06/1999|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 18:44[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        05/06/1999|
+------------------------------------------------+EVENT TIME:        18:00[EDT]|
| NRC NOTIFIED BY:  MARTIN                       |LAST UPDATE DATE:  05/06/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALVE FAILED LOCAL LEAK RATE TEST(LLRT).                                     |
|                                                                              |
| VALVE 3QSS*V4 IS A CHECK VALVE IN THE QUENCH SPRAY SYSTEM AND THE CAUSE OF   |
| THE LLRT FAILURE IS UNKNOWN AND BEING INVESTIGATED, BUT MOST LIKELY MAY BE   |
| DUE TO VALVE DEGRADATION.  WHEN THE RESULTS OF ITS LLRT WERE ADDED TO THE    |
| OTHER CATEGORY "C" VALVES RESULTS, THE TOTAL LEAKAGE EXCEEDED TECHNICAL      |
| SPECIFICATION ALLOWABLE LIMITS OF 43 SCFH (TOTAL MEASURED CATEGORY "C" WAS   |
| 335 SCFH); HOWEVER, THE TOTAL LEAKAGE OF EVERYTHING STILL DID NOT EXCEED THE |
| 0.6La VALUE.  CORRECTIVE ACTION WILL BE TO REPAIR THE VALVE PRIOR TO         |
| STARTUP.                                                                     |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH STATE, LOCAL AND OTHER        |
| GOVERNMENT AGENCIES.                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35687       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 05/06/1999|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 20:33[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        05/06/1999|
+------------------------------------------------+EVENT TIME:        16:14[CDT]|
| NRC NOTIFIED BY:  NACOSTE                      |LAST UPDATE DATE:  05/06/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       23       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE REACTOR WAS MANUALLY SCRAMMED FROM 23.5% POWER.                          |
|                                                                              |
| DURING STARTUP FOLLOWING A REFUELING OUTAGE, THE UNIT EXPERIENCED A STEAM    |
| LEAK ON THE INLET SIDE OF THE OFFGAS PREHEATER  (ASME CLASS 2 PIPING).       |
| TECHNICAL REQUIREMENTS MANUAL (TMR) SECTION  3.4.3 REQUIRES THAT THE         |
| AFFECTED COMPONENT BE ISOLATED IMMEDIATELY, REQUIRING THAT THE MAIN STEAM    |
| ISOLATION VALVES (MSIVs) BE CLOSED.  THE MAIN TURBINE WAS TRIPPED FROM 23.5  |
| % POWER IN ANTICIPATION OF THE INSERTION OF A MANUAL SCRAM WHICH OCCURRED AT |
| 1614 CST.  THE MANUAL SCRAM CAUSED REACTOR VESSEL WATER LEVEL TO GO BELOW    |
| THE LOW SETPOINT LEVEL, WHICH GENERATED A REDUNDANT SCRAM SIGNAL AND         |
| INITIATED THE PCIS ISOLATIONS OF GROUPS 2 (PRIMARY CONTAINMENT), 3 (RWCU), 6 |
| (SECONDARY CONTAINMENT), AND 8 (TIP SYSTEM).  ALL RODS FULLY INSERTED, NO    |
| ECCS INJECTION OCCURRED, AND NO RELIEF VALVES LIFTED.  THE MSIVs WERE CLOSED |
| AT 1632.                                                                     |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT.                           |
+------------------------------------------------------------------------------+