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Event Notification Report for November 26, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/25/2002 - 11/26/2002

                              ** EVENT NUMBERS **

39392  39404  39405  

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|General Information or Other                     |Event Number:   39392       |
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| REP ORG:  GENERAL ELECTRIC COMPANY             |NOTIFICATION DATE: 11/22/2002|
|LICENSEE:  GENERAL ELECTRIC COMPANY             |NOTIFICATION TIME: 13:43[EST]|
|    CITY:  SAN JOSE                 REGION:  4  |EVENT DATE:        11/22/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  11/25/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DALE POWERS          R4      |
|                                                |MOHAMED SHANBAKY     R1      |
+------------------------------------------------+DAVID AYRES          R2      |
| NRC NOTIFIED BY:  JASON POST (fax)             |BRENT CLAYTON        R3      |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |JACK FOSTER          NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| GENERAL ELECTRIC IDENTIFIED THE STABILITY OPTION III PERIOD BASED DETECTION  |
| ALGORITHM Tmin SPECIFICATION HAS A DEFECT                                    |
|                                                                              |
| "Stability solution Option III is implemented in the Oscillation Power Range |
| Monitor (OPRM).   Each OPRM channel contains 18 to 33 OPRM cells (depending  |
| upon plant size).   Each OPRM cell signal is summed from three to four       |
| closely spaced Local Power Range Monitor (LPRM) signals.   Each OPRM cell    |
| signal is processed through the Option Ill detection algorithms to determine |
| when a trip is required.   Trip of one OPRM cell causes its OPRM channel to  |
| trip, and when sufficient OPRM channels trip (one-out-of-two taken twice, or |
| two-out-of-four), a reactor scram is initiated to terminate the              |
| oscillation.                                                                 |
|                                                                              |
| "An OPRM trip is enabled for plant operation within the OPRM Armed Region as |
| defined on the power/flow map.  The Armed Region extends from natural        |
| circulation to 60% of rated core flow.  The licensing basis for the OPRM is  |
| to detect all expected oscillations within the OPRM Armed Region, and        |
| initiate a reactor trip to suppress the oscillation and provide Minimum      |
| Critical Power Limit (MCPR) safety limit protection.                         |
|                                                                              |
| "GE LTR NEDO-31960-A, Supplement 1, 'BWR Owners' Group Long - Term Stability |
| Solutions Licensing Methodology (Supplement 1),' November 1995, describes    |
| the Option III detection algorithms.  The Period Based Detection Algorithm   |
| (PBDA) provides licensing basis MCPR safety limit protection.  Other         |
| algorithms provide defense-in-depth protection.  The PBDA includes two       |
| parameters called Tmin and Tmax.  The PBDA will not evaluate oscillations if |
| the period is less than Tmin or greater than Tmax  because these would not   |
| be indicative of an expected coupled neutronic/thermal - hydraulic           |
| instability.   The LTR specifies that 'typical'  Tmin values are in the      |
| range of 1.0 to 1.4 seconds and 'typical' Tmax values are in the range of    |
| 3.0 to 3.5 seconds.                                                          |
|                                                                              |
| "The expected period of a coupled neutronic/thermal-hydraulic instability    |
| depends upon the fluid transit time through the core, and therefore depends  |
| upon core flow rate.  This has been demonstrated in reactor operation and is |
| predicted by GE computer models.   At high core flow, the expected           |
| oscillation period is shorter.   At low core flow rate, the expected         |
| oscillation period is longer.   The intent of the OPRM is that Tmin and Tmax |
| provide a wide range with adequate margin to the expected oscillation period |
| for operation within the OPRM Armed Region so that all expected coupled      |
| neutronic/thermal-hydraulic instabilities will be detected by the PBDA."     |
|                                                                              |
| * * * * POTENTIALLY AFFECTED PLANTS ADDED TO REPORT BY RIPLEY 11/25/02  * *  |
| * *                                                                          |
|                                                                              |
| The notification identified the following potentially affected plants:       |
|                                                                              |
| Clinton, Brunswick 1, Brunswick 2, Nine Mile Point 2, Fermi 2, Columbia,     |
| Dresden 2, Dresden 3, LaSalle 1, LaSalle 2, Limerick 1, Limerick 2, Peach    |
| Bottom 2, Peach Bottom 3, Quad Cities 1, Quad Cities 2, Perry 1, Susquehanna |
| 1, Susquehanna 2, Hope Creek, Hatch 1, Hatch 2, Browns Ferry 2, Browns Ferry |
| 3                                                                            |
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|General Information or Other                     |Event Number:   39404       |
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| REP ORG:  SPECTRUM TECHNOLOGIES                |NOTIFICATION DATE: 11/25/2002|
|LICENSEE:  CUTLER-HAMMER                        |NOTIFICATION TIME: 16:25[EST]|
|    CITY:  SCHENECTADY              REGION:  1  |EVENT DATE:        11/25/2002|
|  COUNTY:                            STATE:  NY |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  11/25/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN ROGGE           R1      |
|                                                |SUSIE BLACK          NRR     |
+------------------------------------------------+JACK FOSTER VIA FAX  NRR     |
| NRC NOTIFIED BY:  BILL WILLIS                  |                             |
|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| PART 21 INITIAL NOTIFICATION - CUTLER-HAMMER  A200 NEMA SIZE 1 STARTERS      |
|                                                                              |
| "Equipment Identification:  Starter, Non-Reversing, Size 1, 600 VAC, 3 Pole, |
| W/125 VDC coil, Westinghouse/Cutler-Hammer P/N A200M1CS, Type B Thermal      |
| Overloads, Ambient Compensated, Manual Reset Only                            |
|                                                                              |
| "In March 2002, Spectrum Technologies provided 20 Class 1E safety related    |
| Cutler-Hammer A200 NEMA Size 1 starters to Rochester Gas & Electric Company  |
| -  Ginna Station. We had purchased the starters as commercial grade items    |
| from Cutler-Hammer, and dedicated them per EPRI NP5652, method 1, Special    |
| Tests and Inspections. This dedication successfully verified the following   |
| critical characteristics:                                                    |
| Markings                                                                     |
| Dimensions and Configuration                                                 |
| Electrical Functional Attributes, Including:  Insulation Resistance, Current |
| Carrying Capacity, Minimum Pickup and Drop Out Voltage, [and] Time Current   |
| Characteristics of Overload Relay                                            |
|                                                                              |
| "Ginna Station recently advised us that one of the starters had experienced  |
| an open phasing failure. They reported that they noted no current flow on    |
| one phase when measured with a clamp-on ammeter, and that current started to |
| flow when the hand pressure was applied to the moving plunger extension that |
| protrudes out the top of the starter. They also noted that the overall       |
| travel of the plunger appeared to be less than that noted on a similar older |
| vintage starter. They provided the failed starter and the older vintage      |
| starter to us for our investigation. The continuity of all phases was        |
| successfully verified, along with the magnetic pull force of the coil, which |
| was comparable to the older vintage starter. We then mounted the failed      |
| starter on a vertical plate in a horizontal (worst case) orientation,        |
| energized the coil and loaded the main contacts to 27 amps. This condition   |
| was maintained until the temperature stabilized with the highest temperature |
| recorded on the terminals (i.e., 59 [degrees] C to 63 [degrees] with ambient |
| at 20.3 [degrees] C). None of this testing performed could duplicate the     |
| single phasing condition observed by Ginna Station. We verified that the     |
| total stroke of the failed starter was less than that of the earlier vintage |
| starter by as much as 0.059 [inches] by our measurement.                     |
|                                                                              |
| "The failed starter and the earlier vintage starter were provided to         |
| Cutler-Hammer for an OEM evaluation. The results of the OEM evaluation was   |
| e-mailed to our Cutler-Hammer distributor and provided to us on November 21, |
| 2002, a copy is attached. This information has been provided to Ginna        |
| Station, and they advised us today (November 25, 2002) that the starters     |
| have been installed in 11 safety related locations, as follows:              |
| MOV-857A, Residual Heat Removal Pump A Discharge                             |
| MOV-4616, Service Water Isolation in Auxiliary Building (Open & Close        |
| Circuit)                                                                     |
| MOV-860C, Containment Spray Pump B Discharge                                 |
| MOV-813, Component Cooling Water Isolation to Reactor Support Coolers (Open  |
| & Close Circuit)                                                             |
| MOV-700, Residual Heat Removal Pump Suction from Loop A Holt Leg             |
| MOV-878A, Safety Injection Discharge to Loop B                               |
| MOV-856, Residual Heat Removal Suction from Refueling Water Storage Tank     |
| MOV-4780, Service Water Isolation in Screenhouse (Open & Close Circuit)      |
|                                                                              |
| "We are currently expediting Cutler-Hammer to complete an audit at their     |
| manufacturing facility to identify the magnitude of this condition and       |
| specify the date codes effected. We are also expediting Cutler-Hammer to     |
| obtain acceptable replacements for the starters provided to Ginna Station."  |
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|Power Reactor                                    |Event Number:   39405       |
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| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 11/25/2002|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 17:08[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/25/2002|
+------------------------------------------------+EVENT TIME:        16:10[EST]|
| NRC NOTIFIED BY:  CHARLIE MARPLE               |LAST UPDATE DATE:  11/25/2002|
|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID AYRES          R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION TO THE STATE OF FLORIDA CONCERNING DISCHARGE OF A       |
| WEAPON ONSITE                                                                |
|                                                                              |
| "On November 24, 2002, at 1715 hours, a contract security officer            |
| inadvertently discharged his weapon when it was reloaded following routine   |
| maintenance. The accidental weapon discharge was attributed to personnel     |
| error, and no injuries resulted from this event. In accordance with Chapter  |
| 493 of the Florida Statutes, Wackenhut Corporation, the state licensed FPL   |
| security contractor, notified the Florida Division of Licensing of this      |
| event on November 25, 2002, at 1610 hours. This non-emergency notification   |
| is being made pursuant to 10 CFR 5072(b)(2)(xi) due to the notification of   |
| Florida Division of Licensing."                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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