Event Notification Report for November 19, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/18/1999 - 11/19/1999
** EVENT NUMBERS **
36446 36447 36448 36449 36450 36451 36452
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|Power Reactor |Event Number: 36446 |
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| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 11/18/1999|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 06:20[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 11/18/1999|
+------------------------------------------------+EVENT TIME: 03:05[CST]|
| NRC NOTIFIED BY: CHRIS MILLER |LAST UPDATE DATE: 11/18/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|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 N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| ESF ACTUATION - INADVERTENT LEVEL ONE ACTUATION WHILE SHUTDOWN |
| |
| While venting and filling the control rod drive system, an invalid level 1 |
| signal was generated due to an isolation valve leaking past its seat and |
| spiking the transmitters. Because the plant is in a refueling outage, the |
| majority of Division 1 equipment was removed from service, the Division 1 |
| drywell purge compressor did actuate from the invalid signal. Additionally |
| the load shedding and sequencing for Division 1 actuated. The RHR 'A' |
| shutdown cooling pump and service water pump were shed and reloaded. The |
| signal also caused the opening of the RHR 'A' injection valve and started |
| the Division 1 diesel generator. Shutdown cooling flow was never entirely |
| lost as the RHR pump re-started after 5 seconds. |
| |
| All components and actuations have been reset to their pre-existing |
| configurations. |
| |
| The licensee will notify the NRC resident inspector. |
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|Fuel Cycle Facility |Event Number: 36447 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/18/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:55[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/17/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:10[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/18/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |THOMAS KOZAK R3 |
| DOCKET: 0707002 | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF CASTLE | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| BULLETIN 91-01 REPORT - NCSA VIOLATION BASED ON SPACING |
| |
| On 11/17/99, at 1010 hours the Plant Shift Superintendent (PSS) was notified |
| that a Nuclear Criticality Safety Approval (NCSA) requirement was not met. |
| A process operator observed a spacing concern while walking down a Fissile |
| Material Operation in the X-333 Low Assay Withdrawal (LAW) Station. A |
| sample manifold that had been removed from the system was staged less than |
| two feet from other uranium bearing material (UF6 process piping). An F-can |
| used for disposal of used Dalton fitting gaskets was also discovered that |
| violated the spacing requirements of NCSA-PLANT025.A05, which constitutes |
| the loss of one control of the double contingency principal. |
| |
| This violated requirement #3 of NCSA-PLANT062.A02 which states in part. |
| Both favorable and unfavorable types or uncomplicated handling (UH) |
| equipment shall be spaced a minimum of 2 feet edge-to-edge from other |
| uranium bearing equipment. This constitutes a loss of control such that |
| only one double contingency control remains in place. |
| |
| The spacing deficiencies were corrected at 1220 hours under Nuclear |
| Criticality Safety (NCS) engineer approval. |
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|Power Reactor |Event Number: 36448 |
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| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 11/18/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 10:15[EST]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 11/18/1999|
+------------------------------------------------+EVENT TIME: 08:00[EST]|
| NRC NOTIFIED BY: SHAWN SIMON |LAST UPDATE DATE: 11/18/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| OFFSITE NOTIFICATION - ILL GREEN SEA TURTLE |
| |
| A GREEN SEA TURTLE WAS TRANSPORTED TO THE SITE MARICULTURE CENTER FOR |
| MONITORING AND EVALUATION. THE TURTLE WAS DETERMINED TO BE IN POOR HEALTH |
| WITH AN ILLNESS NOT ATTRIBUTED TO PLANT OPERATION. THE LICENSEE NOTIFIED |
| THE STATE OF FLORIDA ENVIRONMENTAL AGENCY. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
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|Power Reactor |Event Number: 36449 |
+------------------------------------------------------------------------------+
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 11/18/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 13:11[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/18/1999|
+------------------------------------------------+EVENT TIME: 12:22[EST]|
| NRC NOTIFIED BY: MUTZ |LAST UPDATE DATE: 11/18/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|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 Refueling |0 Refueling |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| UNESCORTED ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE COMPENSATORY MEASURES |
| TAKEN UPON DISCOVERY. CONTACT THE OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED. |
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|Power Reactor |Event Number: 36450 |
+------------------------------------------------------------------------------+
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| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 11/18/1999|
| UNIT: [1] [2] [] STATE: TN |NOTIFICATION TIME: 15:31[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/18/1999|
+------------------------------------------------+EVENT TIME: 12:20[EST]|
| NRC NOTIFIED BY: CALVIN FIELDS |LAST UPDATE DATE: 11/18/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| MANUAL CONTROL ROOM VENTILATION ISOLATION DUE TO SMOKE |
| |
| At 1220, operators detected smoke in the main control room, but could not |
| readily locate the source. Abnormal Operating Procedure (AOP) N-01 was |
| entered, and operators manually initiated a control room isolation. At 1235, |
| a burnt filter capacitor was located in the annunciator channel 'A' |
| inverter. The inverter was deenergized and annunciator power was transferred |
| to the maintenance source. The annunicators remained operable at all times. |
| At 1338, operators exited AOP N-01 after the smoke cleared and recovery |
| operations were completed. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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|Power Reactor |Event Number: 36451 |
+------------------------------------------------------------------------------+
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| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 11/18/1999|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 17:45[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 06/19/1999|
+------------------------------------------------+EVENT TIME: 02:18[EST]|
| NRC NOTIFIED BY: EDWIN PRICE |LAST UPDATE DATE: 11/18/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 68 Power Operation |68 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT OUTSIDE OF DESIGN BASIS DUE TO 10 CFR PART 50 APPENDIX R ISSUE |
| |
| "An ongoing review of the circumstances pertaining to a decrease in a |
| reactor coolant pump (RCP) oil level has concluded that leakage of the RCP |
| oil collection system onto hot piping constituted a condition outside the |
| design basis. At 2335 on 6/18/99 a control room alarm for low oil pot level |
| on 2A1 RCP Motor was received. Investigation of trends showed that a slow |
| downward trend on 2A1 RCPM lower oil pot level had increased to a rate of |
| 0.5 inches decrease in four hours. Operations calculated that this rate |
| would result in reaching the requirement to trip the 2A1 RCP within about |
| three hours. |
| |
| "Abnormal Procedure AP/2/A/1700/06 was entered and appropriate notifications |
| were made. |
| |
| "Power reduction to <70% was begun at 0020 on 5/19/99 in order to secure the |
| 2A1 RCP prior to receiving the 2A1 ROP Low Oil level Statalarm. Unit power |
| was stabilized at 58% at 0217 on 6/19/99. 2A1 RCP was stopped at 0218 on |
| 6/19/99 with the lower oil pot level reading approximately -1.0 inches. |
| |
| "The lower oil pot was removed and inspected. The cause of the leak was |
| determined to be poor condition of the oil pot sealing surfaces. The |
| aluminum pot had numerous dents and scrapes on the sealing surfaces. |
| Permatex was filling the voids created by the dents and scrapes. Several |
| likely leak paths were noted. Sudden loss of oil was caused by a large clump |
| of the Permatex washing out on the bottom-sealing surface. Gaskets were |
| still soft and pliable and no flaking or disintegration was noted. The |
| Permatex was soft and smearable. The oil pot was replaced by a new steel oil |
| pot. |
| |
| "Another problem noted during the investigation of the leaking oil pot was |
| that the drip pan under the oil pot, which is designed to collect leakage |
| and route it to an oil collection tank in the reactor building basement, was |
| leaking. It was determined approximately 10 gallons of oil had leaked out. |
| The source of the leakage was a poor seal at the gasketed drip pan joint. |
| This joint had been assembled with a thin gasket and very little joint |
| sealant. Following reassembly of the oil pot, the drip pan was reassembled |
| using high temperature RTV on the gasket to achieve a good seal. 2B2 drip |
| pan was removed to investigate a possible oil pan leak and reassembled using |
| the same method. The other Unit 2 drip pans (2A1, 2A2) were inspected and |
| they appeared in good condition with no evidence of leakage. |
| |
| "The design requirements for RCP Oil collection systems are given in 10 CFR |
| 50 Appendix R (iii) (O). The RCP Oil collection system that leaked is |
| considered PAST INOPERABLE. It was assumed that this occurred in the time |
| period since its last inspection because the known cause is degradation of |
| the sealing material over time. |
| |
| "Fire protection uses a defense-in-depth solution to minimize the hazards |
| and effects associated with fires. Even though the oil collection system |
| leaked part of their collected contents they still performed part of their |
| function. Because of the high flash point of the oil used, the oil collected |
| location, and limited oxygen availability; the risk of a significant fire |
| initiation in the reactor building was minimal. The only potential ignition |
| source is thermally hot pipe. Hot pipe is covered with metallic reflective |
| insulation. This jacket would limit oxygen available to fire and thus the |
| potential severity of a fire. A fire at any reactor coolant pump would be |
| limited to that RCP cavity by lack of continuity of combustible materials. |
| Thus the potential for fire propagation was low. |
| |
| "Appendix R scenarios take into account the potential for fire in the |
| reactor building and designed the safe shutdown system features, modified |
| plant equipment, and procedures in order to successfully mitigate any core |
| consequences. |
| |
| "This event is being reported because the RCP lube oil collection system did |
| not meet the UFSAR and Design Basis Document requirements to contain and |
| prevent oil from getting onto hot piping or equipment with a surface |
| temperature above the flashpoint of the oil." |
| |
| The NRC resident inspector has been informed of this condition by the |
| licensee. |
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|Power Reactor |Event Number: 36452 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 11/18/1999|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 19:04[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/18/1999|
+------------------------------------------------+EVENT TIME: 16:03[EST]|
| NRC NOTIFIED BY: JEFF HELSEL |LAST UPDATE DATE: 11/18/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| UNEXPECTED EMERGENCY DIESEL GENERATOR START FOLLOWING MAINTENANCE |
| |
| "After restoration from planned maintenance, the 'A' Diesel Generator was |
| transferred for the 'E' Diesel Generator. When the 'A' diesel Generator |
| control was taken from local to remote, the Operator at the diesel Generator |
| heard air porting from the diesel and it began to start. This was not an |
| expected response. Subsequently, several alarms were received in the Control |
| Room and locally and the diesel appeared to be slowing down. Seconds later |
| it appeared the diesel began to crank up again. At this point, the Operator |
| at the diesel initiated an emergency stop. Investigation into the cause of |
| the auto initiation is ongoing. |
| |
| "This event is an Unplanned Actuation of an Engineered Safety Feature and |
| therefore requires a four hour ENS Notification under 10 CFR |
| 50.72(b)(2)(ii)." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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