ML18153D202
| ML18153D202 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/21/1992 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-655B, NUDOCS 9212240087 | |
| Download: ML18153D202 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 21, 1992 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 COMPONENT COOLING HEAT EXCHANGER CHANNEL HEAD REPLACEMENT Serial No.
91-6558 SPS/MDK/ETS RS Docket Nos.
50-280 50-281 License Nos.
DPR-32 DPR-37 On September 22, 1992, during a 1 O year inservice inspection hydrostatic pressure test, the 'C' component cooling water heat exchanger (CCHX) developed a leak that required a Code repair to the inlet channel head. As stated in our letters of December 6, 1991 (Serial Number 91-655) and February 10, 1992 (Serial Number 91-655A),
and NRC Safety Evaluation dated March 25, 1992, if any channel head degradation was identified in the 'C' CCHX that required a Code repair or prevented the heat exchanger from meeting Section XI operability requirements, the 'C' CCHX channel heads would be repaired during the operating cycle and the entire heat exchanger replaced at the next outage of sufficient duration. As a result of performing this Code repair and our commitment identified above, this letter presents our plan to replace the
'C' CCHX during the next Unit 1 refueling outage presently scheduled for Spring 1994.
We have evaluated two options for replacing the heat exchanger. One option was to replace the heat exchanger during the 1993 Unit 2 refueling outage. The second option was to replace the heat exchanger during the 1994 Unit 1 refueling outage.
This letter advises you of our decision to replace the 'C' CCHX during the_ Unit 1 refueling outage scheduled for Spring 1994, as discussed with Mr. H. Berkow and B.
Buckley on December 17, 1992.
A Code repair has been made on the 'C' component cooling water heat exchanger.
The failure was located in the inlet channel head and was due to general corrosion localized in an area of failed coating. The heat exchanger has satisfactorily completed return-to-service pressure testing. Our repair and subsequent testing have maintained the dedication and the level of quality and safety of this heat exchanger. In addition, we are continuing to monitor the material condition of the channel heads to provide an additional measure of assurance of the operability of the components.
<',) JJ /"I IC,1-J:UO~):)
921224~087 921221 PDR ADOCK 05000280 G
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'The four component cooling water heat exchangers service both units and are located in the Unit 1 turbine building basement. Three of the four component cooling water heat exchangers have been replaced with new heat exchangers that conform to ASME Code requirements.
Our Technical Specifications require two component cooling water heat exchangers to be operable with one unit at power and three heat exchangers to be operable with two units at power. The system is designed to allow any combination of heat exchangers to service either one or both units in configurations where the system can be dedicated to service one unit or cross-tied to service both units.
Based on the physical location, procedural restrictions, satisfactory results of pressure testing, and continued monitoring of the material condition of the channel heads, we plan to replace the 'C' component cooling water heat exchanger during the Unit 1 refueling outage scheduled for Spring 1994.
If you have questions regarding this information, please contact us.
Very truly yours,
~&L~
W. L. Stewart Senior Vice President - Nuclear cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRG Senior Resident Inspector Surry Power Station