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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        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36447       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36448       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36449       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE COMPENSATORY MEASURES   |
| TAKEN UPON DISCOVERY. CONTACT THE OPERATIONS CENTER FOR ADDITIONAL DETAILS.  |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36450       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36451       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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                                   
+------------------------------------------------------------------------------+
| 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.  |
+------------------------------------------------------------------------------+