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Event Notification Report for October 2, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/01/2002 - 10/02/2002

                              ** EVENT NUMBERS **

39234  39235  39236  

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|Power Reactor                                    |Event Number:   39234       |
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| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 10/01/2002|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 16:56[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/01/2002|
+------------------------------------------------+EVENT TIME:        09:42[EDT]|
| NRC NOTIFIED BY:  TIM JOHNSON                  |LAST UPDATE DATE:  10/01/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON           R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| VALID SPECIFIED SYSTEM ACTUATION DURING TESTING ON ENGINEERED SAFETY         |
| FEATURES                                                                     |
|                                                                              |
| "Station was conducting ESF testing on the 1B train with the 1B Diesel       |
| Generator aligned to the 1B essential bus.  While re-aligning from the test  |
| alignment, the 1B emergency breaker tripped open due to a problem with the   |
| Cutler-Hammer control switch.  A valid blackout signal was sensed on the 1B  |
| bus.  The 1B emergency breaker immediately re-closed and the 1B essential    |
| bus was re-energized from the 1B Diesel Generator.  Switch repair is in      |
| progress."                                                                   |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector.                        |
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|Power Reactor                                    |Event Number:   39235       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 10/01/2002|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 17:44[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        10/01/2002|
+------------------------------------------------+EVENT TIME:        08:45[CDT]|
| NRC NOTIFIED BY:  STEVEN A. HENRY              |LAST UPDATE DATE:  10/01/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KRISS KENNEDY        R4      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| UNANALYZED CONDITION RELATING TO CONTROL ROOM EVACUATION                     |
|                                                                              |
| "On October 1 2002, conditions were discovered that if an evacuation of the  |
| Wolf Creek Generation Station (WCGS) control room were required, due to a    |
| fire, necessary steps could not be completed within committed time           |
| requirements. The station is in Mode 1, at 100% power.                       |
|                                                                              |
| "During a timed walk down of procedure OFN RP-017, 'Control Room             |
| Evacuation,' it was identified that operators did not complete Phase A       |
| actions of the procedure in the committed five minutes. Phase A provides     |
| that control of the plant will be established at the Auxiliary Shutdown      |
| Panel (ASP) and isolation of required instrumentation and other devices on   |
| the ASP will be accomplished. Phase A was performed in approximately 8       |
| minutes. This does not meet our commitment to 10 CFR 50 Appendix R as        |
| reflected in the WCGS Fire Protection Plan. The effect of additional time to |
| complete Phase A of the control room evacuation is being further analyzed to |
| determine the safety significance.                                           |
|                                                                              |
| "Based on the guidance provided in NUREG 1022 Revision 2, this situation     |
| meets the criterion of 10CFR50.72(b)(3)(ii)(B) for an 8-hour ENS             |
| notification, as it relates to being in an unanalyzed condition."            |
|                                                                              |
| The Licensee has implemented compensatory measures at 1900 CDT, 10/1/02.     |
|                                                                              |
| The licensee has notified the NRC Resident Inspector                         |
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|General Information or Other                     |Event Number:   39236       |
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| REP ORG:  GENERAL ELECTRIC COMPANY             |NOTIFICATION DATE: 10/01/2002|
|LICENSEE:  GENERAL ELECTRIC COMPANY             |NOTIFICATION TIME: 20:24[EDT]|
|    CITY:  San Jose                 REGION:  4  |EVENT DATE:        10/01/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/01/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PETE ESELGROTH       R1      |
|                                                |JAY HENSON           R2      |
+------------------------------------------------+SONIA BURGESS        R3      |
| NRC NOTIFIED BY:  JASON S. POST                |KRISS KENNEDY        R4      |
|  HQ OPS OFFICER:  MIKE NORRIS                  |WILLIAM DEAN         NRR     |
+------------------------------------------------+VERN HODGE           NRR     |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| PART 21.21 REPORT INVOLVING STABILITY OPTION III                             |
|                                                                              |
| "Subject: Stability Option III: Possible Successive Confirmation Count       |
| Resets                                                                       |
|                                                                              |
| "This letter provides notification of a 60 Day Interim Report per  21.21    |
| (a)(2) for plants that have selected stability long-term solution Option     |
| III. The basis for this notification is that GE Nuclear Energy (GE) has not  |
| completed the evaluation of a potential problem with the algorithm that      |
| provides the licensing basis Minimum Critical Power Ratio (MCPR) Safety      |
| Limit protection for stability Option III. The algorithm determines          |
| Successive Confirmation Count (SCC) of an oscillating power signal. A        |
| reactor trip is generated when SCC and oscillation amplitude reach their     |
| trip setpoints in accordance with the Option III and reactor protection      |
| system configuration. The concern is that the oscillation period could       |
| change for an oscillation that initiates while reactor state conditions are  |
| changing rapidly (e.g., during a two-recirculation pump trip event) and      |
| cause the SCC to reset, thus delaying the reactor scram.                     |
|                                                                              |
| "GE believes that there is low potential for the MCPR Safety Limit to be     |
| violated as a result of this concern. However, a 60 Day Interim Report is    |
| required since the evaluation has not been completed. Further information is |
| provided in the attached notification.                                       |
|                                                                              |
| "(ii) Identification of the facility, the activity, or the basic component   |
| supplied for such facility or such activity within the United States which   |
| fails to comply or contains a defect:                                        |
|                                                                              |
| "The affected basic component is the Period Based Detection Algorithm (PBDA) |
| of stability long-term solution Option III. The PEDA provides the licensing  |
| basis MCPR Safety Limit protection for anticipated coupled thermal           |
| hydraulic-neutronic reactor instabilities. The concern is that the           |
| Successive Confirmation Count (SCC) could reset if an oscillation develops   |
| while reactor state conditions are changing rapidly (e.g., during a two      |
| recirculation pump trip event) and delay a reactor scram beyond that assumed |
| in the licensing basis analysis. The algorithm is more susceptible to SCC    |
| resets with a period tolerance that is near to the minimum allowed by        |
| licensing documents (e.g., 50 msec). SCC resets are less likely with higher  |
| period tolerance values (e.g., 100 to 300 msec).                             |
|                                                                              |
| "(iii) Identification of the firm constructing the facility or supplying the |
| basic component which fails to comply or contains a defect:                  |
|                                                                              |
| "GE Nuclear Energy, San Jose, California                                     |
|                                                                              |
| "(iv) Nature of the defect or failure to comply and safety hazard which is   |
| created or could be created by such defect or failure to comply:             |
|                                                                              |
| "A reactor scram is only initiated by the PBDA when the SCC exceeds the      |
| count setpoint and the oscillation amplitude exceeds the amplitude setpoint  |
| The licensing basis is that the SCC will exceed the count setpoint before    |
| the amplitude reaches the amplitude setpoint. If the SCC resets, then the    |
| amplitude could exceed the amplitude setpoint before SCC reaches the count   |
| setpoint. This could lead to violation of the MCPR Safety Limit.             |
|                                                                              |
| "If scram is delayed, boiling transition could be experienced on a portion   |
| of some fuel bundles. This would be a violation of a Technical Specification |
| Safety Limit and is reportable under 10 CFR 21. However, it would not        |
| produce a significant safety hazard or threat to public health and safety.   |
|                                                                              |
| "(v) The date on which the information of such defect or failure to comply   |
| was obtained:                                                                |
|                                                                              |
| "(vi) In the case of a basic component which contains a defect or failure to |
| comply, the number and locations of all such components in use at, supplied  |
| for, or being supplied for one or more facilities or activities subject to   |
| the regulations in this part:                                                |
|                                                                              |
| "A defect has not been confirmed to exist. The potentially affected plants   |
| are listed in Attachment 2.                                                  |
|                                                                              |
| "(vii) The corrective action which has been, is being, or will be taken; the |
| name of the individual or organization responsible for the action; and the   |
| length of time that has been or will be taken to complete the action (note,  |
| these are actions specifically associated with the identified Reportable     |
| Condition):                                                                  |
|                                                                              |
| "GE has communicated this concern to the BWR Owners' Group Potential Issues  |
| Resolution Team (PIRT) and to the Stability Detect & Suppress Committee.     |
|                                                                              |
| "GE is continuing to evaluate the potential for the SCC to be reset for      |
| current licensed reactor operating conditions. This effort will be completed |
| by November 18, 2002.                                                        |
|                                                                              |
| "(viii) Any advice related to the defect or failure to comply about the      |
| facility, activity, or basic component that has been, is being, or will be   |
| given to purchasers or licensees:                                            |
|                                                                              |
| "It is recommended that potentially affected licensees keep informed through |
| the BWR Owners' Group. No specific plant actions are recommended at this     |
| time."                                                                       |
|                                                                              |
| Plants listed on Attachment 2                                                |
| Clinton, Brunswick 1& 2, Nine Mile Point 2, Fermi 2, Columbia, Dresden 2 &   |
| 3, LaSalle 1 & 2, Limerick 1 & 2, Peach Bottom 2 & 3, Quad Cities 1 & 2,     |
| Perry 1, Susquehanna 1 & 2, Hope Creek, Hatch 1 & 2, and Browns Ferry 1, 2 & |
| 3.                                                                           |
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