Part 21 Report - 2001-110

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|Power Reactor                                    |Event Number:   37788       |
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| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 02/28/2001|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 14:42[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        01/12/2001|
+------------------------------------------------+EVENT TIME:        12:08[EST]|
| NRC NOTIFIED BY:  KELLEY MARSH                 |LAST UPDATE DATE:  02/28/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEPHEN CAHILL       R2      |
|10 CFR SECTION:                                 |VERN HODGE           NRR     |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |RICHARD CONTE        R1      |
|                                                |ANTON VEGEL          R3      |
|                                                |LINDA HOWELL         R4      |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Startup          |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT
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| 10 CFR  PART 21 REPORT REGARDING A SUBSTANTIAL SAFETY HAZARD WITH A WOODWARD |
| GOVERNOR EGB UNIT                                                            |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 1/12/01, V. C. Summer Nuclear Station (VCSNS) determined that a          |
| Substantial Safety Hazard could exist with Woodward governor EGB units       |
| failing to properly control the Emergency Diesel Generator [(EDG)].  A       |
| condition report (received on 1/12/01) from B. F. Goodrich/Fairbanks Morse   |
| indicated there was binding of the terminal shaft internal to an EGB unit    |
| removed from the 'A' EDG at VCSNS.  The disassembly inspection found that    |
| the binding of the terminal shaft was due to the use of clamping screws,     |
| which were 1/8 inch longer than specification, resulting in binding on the   |
| output servo piston connecting rod.                                          |
|                                                                              |
| "This error was made during the prior refurbishment of the EGB by Engine     |
| Systems Inc. (ESI), the Woodward Governor nuclear representative, on         |
| 2/24/00.  The use of the longer screws resulting in binding in the unit is   |
| considered a defect, which was introduced during the repair process by ESI.  |
|                                                                              |
| "[VCSNS] utilizes these EGB units on both the 'A' and 'B' EDGs.  The above   |
| condition produced severe frequency oscillations on the output of the 'A'    |
| EDG.  This condition could have been introduced to any EGB during            |
| refurbishment by ESI, passed acceptance testing, and be present on both      |
| EDGs.  In an emergency condition, both EDGs could fail, resulting in the     |
| loss of safety function for the emergency on-site power supply.              |
|                                                                              |
| "The EGB units currently installed on both EDGs have been refurbished by     |
| Fairbanks Morse with properly specified parts.  Fairbanks Morse will perform |
| all future EGB refurbishment work for VCSNS.  Other cause and corrective     |
| actions associated with the governor issues are being addressed under Root   |
| Cause Analysis report RCA 01-0235, 'Diesel Generator 'A' Governor Problems.' |
| "                                                                            |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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