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Event Notification Report for May 19, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/18/2000 - 05/19/2000

                              ** EVENT NUMBERS **

36907  36983  36986  37010  37011  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36907       |
+------------------------------------------------------------------------------+
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| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 04/19/2000|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 21:36[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/19/2000|
+------------------------------------------------+EVENT TIME:        18:16[EDT]|
| NRC NOTIFIED BY:  ALLEN HARROW                 |LAST UPDATE DATE:  05/18/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           R2      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|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          N       0        Cold Shutdown    |0        Cold Shutdown    |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| FILTERED EXHAUST FANS CANNOT BE OPERATED IN PARALLEL                         |
|                                                                              |
| "Based on Unit 1H and 1J emergency bus logic testing performed on 4/18/00    |
| and 4/19/00 in accordance with 1-OPT-ZZ-001 and 1-OPT-ZZ-002, it has been    |
| concluded that the Cat 1 Filtered Exhaust Fans, 1-VS-F-58A & B, will not     |
| operate in parallel without tripping one or both fans. As a result, an event |
| or condition that alone could have prevented the fulfillment of a safety     |
| function of structures or systems that are needed to control the release of  |
| radioactive material, or mitigate the consequences of an accident exists for |
| Surry Units 1 and 2. This condition is reportable in accordance with 10 CFR  |
| 50.72(b)(2)(iii).                                                            |
|                                                                              |
| "Both fans have been tested by operating the fans individually. This testing |
| has determined that operation and performance of each fan is entirely        |
| satisfactory when operated independently.                                    |
|                                                                              |
| "The current system alignment is that one of the two fans is in the          |
| pull-to-lock position, and the other fan is in automatic stand-by. In this   |
| configuration, one fan is operable, and fully capable of performing its      |
| required functions. Unit 2 entered a 7 day Technical Specification 3.22.B    |
| action statement on 4/18/00 at 1240 hours as a result of this condition.     |
|                                                                              |
| "The Surry Emergency Operating Procedures provide required directions to     |
| place a Cat 1 Filtered Exhaust Fan in service, if the fans fail to           |
| automatically start upon initiation of a Safety Injection. In the current    |
| configuration, if the operable Cat 1 Filtered Exhaust fan fails to start,    |
| the fan that is currently in PTL can be immediately placed in service."      |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| * * * UPDATE ON 5/18/00 @ 1243 BY HARROW TO GOULD * * *      RETRACTION      |
|                                                                              |
| NUREG 1022, Event Reporting Guidelines for10CFR50.72 and 50.73. states that  |
| "Reasonable operator actions to correct minor problems may be considered;    |
| however, heroic actions and unusually perceptive diagnoses, particularly     |
| during stressful situations should not be assumed."                          |
|                                                                              |
| Both CAT 1 FiItered Exhaust Fans were proven to operate satisfactorily when  |
| tested individually, and only one fan is needed to meet the system design    |
| requirements. If both fans had tripped after automatically starting from a   |
| Safety Injection signal, the Emergency Operating Procedures (EOP's) would    |
| direct that one fan be started.  This is accomplished from the control room, |
| and does not require unusual actions from the operator.  The Surry DBA Dose  |
| Analysis assumes that filtration of ECCS leakage begins 30 minutes           |
| post-accident, which is ample time to perform the EOP action of starting a   |
| Filtered Exhaust Fan if none are running.                                    |
|                                                                              |
| Based on the above review of the event and the information in NUREG 1022, it |
| has been determined that this event was not immediately reportable, as       |
| existing Emergency Operating Procedures would ensure that at least one fan   |
| is running within the required time after a Safety Injection signal is       |
| received.                                                                    |
|                                                                              |
| This notification is being made to retract the report made on 4/19/00 based  |
| on the above discussion.                                                     |
|                                                                              |
| The NRC Resident Inspector was notified.        Notified the Reg 2           |
| RDO(Wert).                                                                   |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36983       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 05:25[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/08/2000|
+------------------------------------------------+EVENT TIME:        03:56[EDT]|
| NRC NOTIFIED BY:  RANDY HAISLET                |LAST UPDATE DATE:  05/18/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POST-ACCIDENT SAMPLING SYSTEM ISOLATION DURING TAGOUT                        |
|                                                                              |
| While performing a tagout on the 'A' train of the post-accident sampling     |
| system (PASS) H2/O2 sampling system, solenoid isolation valve SV-5065-20B,   |
| which is a 'B' train valve, closed unexpectedly. The licensee restored the   |
| 'A' train of PASS H2/O2 monitoring to service and closed the redundant       |
| solenoid isolation valve in the 'B' train. The licensee declared valve       |
| SV-5065-20B inoperable.                                                      |
|                                                                              |
| After review of system electrical diagrams, the licensee determined that the |
| closure of valve SV-5065-20B was appropriate, although its closure was not   |
| anticipated in the tagout procedure. The NRC resident inspector has been     |
| informed of this event by the licensee.                                      |
|                                                                              |
| * * * RETRACTION 1653 5/18/2000 FROM ERIC OLSON TAKEN BY BOB STRANSKY * * *  |
|                                                                              |
| The licensee is retracting this notification in accordance with NUREG-1022,  |
| Section 3.3.2, Paragraph 5. The licensee has determined that this event did  |
| not constitute an ESF actuation because only a portion of the system logic   |
| tripped. The NRC resident inspector has been informed of this retraction by  |
| the licensee. Notified R1DO (Lew).                                           |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36986       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 20:56[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/08/2000|
+------------------------------------------------+EVENT TIME:        20:25[EDT]|
| NRC NOTIFIED BY:  JOSEPH GIAR                  |LAST UPDATE DATE:  05/18/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - FOULING OF THE REACTOR BUILDING CLOSED COOLING WATER  |
| HEAT EXCHANGER (RBCCW HX).                                                   |
|                                                                              |
| Surveillance testing has identified fouling of the Salt Service Water (SSW)  |
| side of the RBCCW HX.  The extent of the fouling on one of the two heat      |
| exchangers would prevent design basis containment heat removal post-accident |
| at maximum design basis ultimate heat sink (UHS) temperature (75F).         |
| Engineering evaluation has determined that design basis heat removal can be  |
| achieved with UHS temperature less than 70F.  Periodic evaluation will be   |
| performed to ensure that additional fouling has not further degraded the     |
| heat exchangers heat transfer capability.                                    |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
|                                                                              |
| * * * RETRACTION 1653 5/18/2000 FROM ERIC OLSON TAKEN BY BOB STRANSKY * * *  |
|                                                                              |
| The licensee has determined that the unit was not operated outside of the    |
| design basis. At the time of the report, the seawater temperature was 50F.  |
| Therefore, the licensee is retracting this notification in accordance with   |
| NUREG-1022, Section 3.2.4. The NRC resident inspector has been informed of   |
| this retraction by the licensee. Notified R1DO (Lew).                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37010       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 05/18/2000|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 09:43[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        05/18/2000|
+------------------------------------------------+EVENT TIME:        07:30[EDT]|
| NRC NOTIFIED BY:  R. WESLEY                    |LAST UPDATE DATE:  05/18/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEN WERT             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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING THE FAILURE OF A MAIN DAM SKIMMER GATE TO     |
| CLOSE                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The] Federal Energy Regulatory Commission (FERC) was notified at 0730 on   |
| 05/18/00 in accordance with 18CFR12.10(a)(1) for a condition affecting the   |
| safety of the project."                                                      |
|                                                                              |
| "Skimmer gate 1B at the main dam failed to close under normal operating      |
| conditions.  The gate is currently open, providing minimum flow.  Corrective |
| action is in progress."                                                      |
|                                                                              |
| The licensee stated that the skimmer gate is used to provide minimum flow    |
| downstream to the river and to provide adequate level control of the main    |
| reservoir for the lake (which supplies cooling water to the plant).  The     |
| required downstream flow of 40 scfm is currently being maintained.           |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37011       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OKLAHOMA GAS & ELECTRIC              |NOTIFICATION DATE: 05/18/2000|
|LICENSEE:  OKLAHOMA GAS & ELECTRIC              |NOTIFICATION TIME: 17:16[EDT]|
|    CITY:                           REGION:  4  |EVENT DATE:        05/17/2000|
|  COUNTY:  MUSKOGEE                  STATE:  OK |EVENT TIME:             [CDT]|
|LICENSE#:  35-19819-03           AGREEMENT:  N  |LAST UPDATE DATE:  05/18/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BILL JONES           R4      |
|                                                |BILL REAMER          NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  B. W. HALL                   |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING RADIOACTIVE SOURCE                                                   |
|                                                                              |
| The licensee reported that a 200 mCi Cs-137 source was discovered to be      |
| missing from a group of sources removed from the Muskogee Power Plant for    |
| disposal. Several Omart model SHDP source holders (with sources) were        |
| transferred to Radiation Technology, Inc., a contractor, for disposal. These |
| source holders had been stored in a warehouse at the power plant for some    |
| time before being transferred to the contractor. The licensee was notified   |
| on 5/17/2000 by the contractor that one of the source holders was empty. The |
| licensee has searched their facility for the source but has been unable to   |
| locate it.                                                                   |
|                                                                              |
| The licensee has already contacted NRC Region 4 (L. Howell).                 |
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