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 |
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|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 | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021