ML19093B066

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Forwarding Table 4.3-2, Which Was Omitted from Revision 1 to Steam Generator Program, Surry Power Station, Unit Nos. 1 & 2, Submitted on 12/2/1977, Serial No. 532
ML19093B066
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/14/1977
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Case E, Reid R
Office of Nuclear Reactor Regulation
References
Serial No. 532-A
Download: ML19093B066 (2)


Text

VIRGINIA ELECTRIC .A.ND POWER

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RIOHMOND, VIRGINIA 23261 ;t '*,_,- .::Jt j '$~fj'a "'ro.

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ti Mr. Edson G. Case, Acting Director Serial*-NP,d J;~,-.

Office of Nuclear Reactor Regulation PO&M/HSM:bep'mc Attn: Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 Docket Nos. 50-280 U. S. Nuclear Regulatory Commission 50-281 Washington, D. C. 20555 License Nos. DPR-32 DPR-37

Dear Mr. Case:

Attached herewith is 40 copies of Table 4.3-2 which was inadvertantly

  • omitted from our Revision 1 to the "Steam Generator*Prog:tam, Surry Power Station, Unit Nos. 1 and 2" which was submitted on.December 2, 1977, Serial No. 532. This table should be entered in the above document as instructed on the Revision 1 instructions sheet.

Very truly yours, Zt;. m. ~la?:v7:Y C. M. Stallings Vice President - Power Supply and Production Operations Attachment cc: Mr. James.P. O'Reilly, Director Region II

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77 2.:soo 11.t-s I I

  • Table 4.3-2

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COMPARISON OF DESIGN PARAMETERS FOR EXISTING AND REPLACEMENT.STEAM.GENERATORS ON SURRY UNITS i*AND 2 Primary Side Volume Unchanged Secondary Side Volume Unchanged Number of Tubes Decreased by 46 Tube O.D. Unchanged Wall Thickness Unchanged Primary Pressure Drop Decreased by 0.1 psi Fouling Factor Unchanged r Heat Transfer Area Unchanged I Flow Area Decreased by 1\,1. 5%

Equivalent Length Increased by 1\,1. 5%.

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