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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021