RC-93-0021, Application for Amend to License NPF-12,revising TS Bases 3/4.3.1 & 3/4.3.2 to Incorporate Issuance of Amend 108 Which Revised ESFs Response Times to Account for Sequential Stroking of Outlet Isolation Valves for RWST & VCT

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Application for Amend to License NPF-12,revising TS Bases 3/4.3.1 & 3/4.3.2 to Incorporate Issuance of Amend 108 Which Revised ESFs Response Times to Account for Sequential Stroking of Outlet Isolation Valves for RWST & VCT
ML20127P433
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 01/29/1993
From: Skolds J
SOUTH CAROLINA ELECTRIC & GAS CO.
To: George Wunder
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20127P436 List:
References
RC-93-0021, RC-93-21, NUDOCS 9302010286
Download: ML20127P433 (1)


Text

_ _ _ - _ _ ~ . _ - _ _ _ _ _ _ _ _ - _ _

i t 4 Sr th Car:line Dectric & Gas Company ohn k e -

  • . .ser,kinsville. CC 2000$ Nuct26r Opstetions '

, (803) 345 4040 1

-SCE&G- -

~"

January 29.-1993  !

Reply to: RC-93-0021l l l

Document Control Desk '!

U. S. Nuclear Regulatory Commission ,

Washington, DC 20555  ;

Attention: Mr. George F. -Wunder .

Gentlemen:

Subject:

VIRGIL C. SUMMER-NUCLEAR STATION -

DOCKET NO. 50/395 OPERATING LICENSE Nu. NPF-12 {~

REVISION TO TECHNICAL SPECIFICATION BASES 3/4.3.1 AND 3/4.3.2, TSP 890022, AMENOMENT 108 _;

Enclosed is a revision to the Technical Specification Bases 's/t 3.1 and j 3/4.3.2. This revision incorporates the -issuance of Amendment- No.108 which revised the Engineer _ing Safety Features response times' to account- for- the- t sequential stroking of the outlet isolation valves for- theLRefueling ' Water' '

StorageTank(RWST)andVolbmeControlTank-(VCT).

This revision provides the conservative assumptions for the position of the_ '

RWST and VCT outlet valves upon which the plant accident analyses are . based. -

Non-LOCA safety analysis assumes that borated water is available when the VCT isclation valves are closed, following the opening of the" RWST isolation valves; LOCA safety analysis assumes that . injection _ flow is: available- +

regardless of the source.- The Determination- of t No :Significant = Hazards- .

Consideration, as well as the Safety Evaluation providedi with .SCE&G's amendment request of April 15.- 1992, support -the revision 'of'- the subject- -

bases.

Should you have any questions concerning this issue, please call' Mr. Manuel -!

W. Gutierrez at (803) 345-4392 at your convenience.

Very truly yours, John L. Skolds MWG:smd l Enclosure c: 0. W. Dixon NRC' Resident-Inspector l R. R. Mahan J. B. Knotts Jr.. +

R. J. White NSRC-S. D. Ebneter RTS_(TSP 890022) ~

General Managers file-(813.20) 9302010286 930129 E DR_ ADOCK-l0500g5 Q()()'$4 _. LNUCLEAR~ EXCELLENCE - A SUtHER TRADITION! g _

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