ML033320008

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Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors - Supplemental Letter
ML033320008
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/18/2003
From: Byrne S
South Carolina Electric & Gas Co
To: Cotton K
Document Control Desk, Office of Nuclear Reactor Regulation
References
BL-03-001, RC-03-0236
Download: ML033320008 (2)


Text

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Stephen A. Byrne Senior Vice President, Nuclear Operations 803.345.4622 A SCANA COMPANY November 18, 2003 RC-03-0236 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Ms. K. R. Cotton

Dear Sir / Madam:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 RESPONSE TO NRC BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS - SUPPLEMENTAL LETTER

Reference:

S. A. Byrne to Document Control Desk,Bulletin 2003-01 response, dated August 6, 2003, RC-03-0164 South Carolina Electric & Gas Company (SCE&G) acting for itself and as agent for South Carolina Public Service Authority, hereby submits a correction letter to the Bulletin response referenced above. Verification activities occurring during the current refueling outage have identified an incorrect sequence in the referenced letter. This sequence describes containment closeout activities prior to Mode 4 of various plant organizations. These activities include walkdown inspections and documentation to confirm that foreign material and debris have been removed as appropriate.

The correct sequence for this activity is that once plant maintenance and modification activities are completed, the Quality Control organization is notified by outage management to perform the containment closeout inspection (actually two part - preliminary and final). This inspection is performed in accordance with Quality Systems procedure (QSP) 522. After the final QC inspection, the entire Reactor Building is declared and maintained a foreign materials exclusion (FME) area.

The operations closeout inspection, performed in accordance with Surveillance Test procedure (STP) 109.001, is performed after completion, or in conjunction with the final QC walkdown inspection, and is the final inspection performed before the lights are turned off in the Reactor Building.

A \\ c SCE&G I Virgil C. Summer Nuclear Station

  • P. 0. Box 88. Jenkinsville, South (arolina 29065.T (803) 345.5209 www.scafno.com

Document Control Desk Letter 0-C-03-1897 RC-03-0236 Page 2 of 2 Should you have questions, please call Mr. Ron Clary at (803) 345-4757.

I certify under penalty of perjury that the information contained herein is true and correct.

Executed on Stephen A. Byrne Senior Vice President, Nuclear Operations PAR/SAB/dr c:

N. 0. Lorick N. S. Carns T. G. Eppink R. J. White L. A. Reyes K. R. Cotton K. M. Sutton K. Leonelli D. A. Baker NRC Resident Inspector NSRC RTS (C-03-1897)

File (815.02)

DMS (RC-03-0236)